http://fispact.ukaea.uk/wiki/api.php?action=feedcontributions&user=Michael+Fleming&feedformat=atomFISPACT-II Wiki - User contributions [en]2024-03-29T15:08:22ZUser contributionsMediaWiki 1.26.2http://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=922Main Page2018-03-22T15:36:26Z<p>Michael Fleming: /* Overview */</p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform serves as an online resource for code users which draws heavily from the [http://www.ccfe.ac.uk/FISPACT-II/documentation/UKAEA-R18001.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [https://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2017, HEIR-0.1, ENDF/B.VIII.0, JEFF-3.3, JENDL-4.0, and CENDL-3.1 international libraries, which are complemented with the latest decay and fission yield data, including the most recent GEFY-6.1 data. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
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== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Supported systems]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
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{{Col-3}}<br />
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=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
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=== Resources for users ===<br />
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*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
*[[Docker images]]<br />
{{col-end}}<br />
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== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub]<br />
* [https://github.com/fispact/ FISPACT-II GitHub]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:aquamarine;width:10%;" | 4.0<br />
| style="width:10%;" | Feb 2018<br />
| This release includes code extensions to handle high-energy (MF=10) nuclear data forms including the HEIR and HEAD libraries, the addition of non-neutron covariances for uncertainty propagation, addition of triton- and helion-induced simulation, new JSON output formats and various bug-fixes. The code now has regression testing, with automated builds tested on more than 100 operating system versions. The base Docker images used for tests can be found on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker hub]. Reference outputs for these systems can be found on the system_tests folder. All new nuclear data libraries, including TENDL-2017, JEFF-3.3 and ENDF/B-VIII were processed and tested with this new version. A new python package [https://github.com/fispact/pypact pypact] for output parsing was also released. <br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=User_licences&diff=921User licences2018-03-22T14:50:41Z<p>Michael Fleming: </p>
<hr />
<div>FISPACT-II is licenced and distributed directly through the UKAEA. Enquiries can be made through the FISPACT-II contact form on the [http://fispact.ukaea.uk/contact/ project site] or by finding the relevant staff member contact on the [http://www.ccfe.ac.uk/researchers.aspx CCFE researchers page].<br />
<br />
The table below gives a break down of the licences. Note that: (1) research licences are only for academic or public sector research establishments, (2) research licences at a nominal fee are available for UK universities and close collaborators and (3) research licenses specifically forbid use in contract work. <br />
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{| class="wikitable"<br />
! rowspan="2" style="text-align: center;" | FISPACT-II Item<br />
! colspan="2" style="text-align: center;" | Licence<br />
|-<br />
| style="text-align: center;" | Commercial<br />
| style="text-align: center;" | Research<br />
|-<br />
| - Executable and all data sets<br />
- One year maintenance and upgrades<br />
| style="text-align: center;" | £30k<br />
| style="text-align: center;" | £15k<br />
|-<br />
| - Annual maintenance and upgrades<br />
| style="text-align: center;" | £4.5k<br />
| style="text-align: center;" | £2.25k<br />
|-<br />
| - Source code (+50% of Exec. licence)<br />
| style="text-align: center;" | £15k<br />
| style="text-align: center;" | £7.5k<br />
|-<br />
| - Training<br />
| rowspan="1" colspan="2" style="text-align: center;" | Price on Application<br />
|}<br />
<br />
The OECD-NEA Data Bank offers a licencing and distribution service through the various members states. Version 4.0 is available as NEA-1890:<br />
<br />
[http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ NEA-1890 FISPACT-II: Inventory Simulation Platform for Nuclear Observables and Materials Science]<br />
<br />
Please note that these distributions come with specific licence agreements which include many limitations, for example forbidding use in commercial applications.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Keyword:USEXSEXTRA&diff=920Keyword:USEXSEXTRA2018-03-22T10:32:29Z<p>Michael Fleming: Created page with " {{big|'''USEXSEXTRA'''}} ---- The '''USEXSEXTRA''' keyword instructs the collapse step to use the cross section data from the <tt>xs_extra</tt> stream in preference to data..."</p>
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<div><br />
{{big|'''USEXSEXTRA'''}}<br />
<br />
----<br />
<br />
The '''USEXSEXTRA''' keyword instructs the collapse step to use the cross section data from the <tt>xs_extra</tt> stream in preference to data in the <tt>xs_endf</tt> stream. It is only implemented in the read library keywords phase and so cannot be changed for subsequent collapses in the inventory phase. The keyword has no effect for EAF data.<br />
<br />
Typically, this keyword is used to extract data that has already been spliced using the [[Keyword:USESPALLATION | USESPALLATION]] keyword. '''USEXSEXTRA''' requires that the stream <tt>xs_extra</tt> is defined in the files file, otherwise a fatal error message will be issued.<br />
<br />
To add the <tt>xs_extra</tt> stream add the lines to the files file:<br />
<br />
# Extra cross section data<br />
xs_extra ./xs_extra<br />
<br />
where the second argument is the path to the directory containing the replacement cross section files.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Keyword:USESPALLATION&diff=919Keyword:USESPALLATION2018-03-22T10:28:50Z<p>Michael Fleming: </p>
<hr />
<div><br />
{{big|'''USESPALLATION''' ''cutoff-energy nnuc''}}<br><br />
{{big|''nuc(i), i''}}''=''{{big|''1,nnuc''}}<br />
<br />
----<br />
<br />
This keyword, added in version 4.0, merges data from the cross-section library on stream <tt>xs_endf</tt> with the spallation cross-section data on stream <tt>sp_endf</tt>. The merged cross-section data files are stored in the directory mapped to stream <tt>xs_extra</tt>. <br />
<br />
The ''cutoff-energy'' is given in MeV and specifies the energy at which the use of <tt>xs_endf</tt> is switched to <tt>sp_endf</tt>. The ''nnuc'' value specifies the number of isotopes that are to be spliced. If <tt>0</tt> is set for ''nnuc'', the keyword causes ''all'' isotopes to be spliced for which there is both a file in <tt>xs_endf</tt> and <tt>sp_endf</tt>. Following these options, the user must specify the ''nnuc'' number of isotopes.<br />
<br />
An example of the use of this keyword is:<br />
<br />
PROJ 3<br />
USESPALLATION 100.0 4<br />
Pb204<br />
Pb206<br />
Pb207<br />
Pb208<br />
GETXS 1 162<br />
<br />
In this case the set of stable lead isotopes are spliced for proton-induced reactions. Note that the HEIR library, released with <tt>FISPACT-II</tt> version 4.0 and above, provides proton-induced reaction data for 2095 isotopes, typically with over 1000 residual products per file. This can introduce several million entries to the rate equation matrix, requiring significantly more computer resources. An example calculation is provided in the [[Getting started examples | getting started examples]].<br />
<br />
The library merging only needs to be done once for a given cutoff energy. Subsequent collapse runs may be performed using the [[Keyword:USEXSEXTRA | '''USEXSEXTRA''']] keyword. NOTE that the library files from previous runs will be used if they remain in the <tt>xs_extra</tt> directory. It is recommended that the contents of the <tt>xs_extra</tt> directory be removed before subsequent runs using the '''USESPALLATION''' are performed.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Keyword:USESPALLATION&diff=918Keyword:USESPALLATION2018-03-22T10:28:34Z<p>Michael Fleming: Created page with " {{big|'''USESPALLATION''' ''cutoff-energy nnuc''}}<br> {{big|''nuc(i), i''}}''=''{{big|''1,nnuc''}} ---- This keyword, added in version 4.0, merges data from the cross-sect..."</p>
<hr />
<div><br />
{{big|'''USESPALLATION''' ''cutoff-energy nnuc''}}<br><br />
{{big|''nuc(i), i''}}''=''{{big|''1,nnuc''}}<br />
<br />
----<br />
<br />
This keyword, added in version 4.0, merges data from the cross-section library on stream <tt>xs_endf</tt> with the spallation cross-section data on stream <tt>sp_endf</tt>. The merged cross-section data files are stored in the directory mapped to stream <tt>xs_extra</tt>. <br />
<br />
The ''cutoff-energy'' is given in MeV and specifies the energy at which the use of <tt>xs_endf</tt> is switched to <tt>sp_endf</tt>. The ''nnuc'' value specifies the number of isotopes that are to be spliced. If <tt>0</tt> is set for \emph{nnuc}, the keyword causes ''all'' isotopes to be spliced for which there is both a file in <tt>xs_endf</tt> and <tt>sp_endf</tt>. Following these options, the user must specify the ''nnuc'' number of isotopes.<br />
<br />
An example of the use of this keyword is:<br />
<br />
PROJ 3<br />
USESPALLATION 100.0 4<br />
Pb204<br />
Pb206<br />
Pb207<br />
Pb208<br />
GETXS 1 162<br />
<br />
In this case the set of stable lead isotopes are spliced for proton-induced reactions. Note that the HEIR library, released with <tt>FISPACT-II</tt> version 4.0 and above, provides proton-induced reaction data for 2095 isotopes, typically with over 1000 residual products per file. This can introduce several million entries to the rate equation matrix, requiring significantly more computer resources. An example calculation is provided in the [[Getting started examples | getting started examples]].<br />
<br />
The library merging only needs to be done once for a given cutoff energy. Subsequent collapse runs may be performed using the [[Keyword:USEXSEXTRA | '''USEXSEXTRA''']] keyword. NOTE that the library files from previous runs will be used if they remain in the <tt>xs_extra</tt> directory. It is recommended that the contents of the <tt>xs_extra</tt> directory be removed before subsequent runs using the '''USESPALLATION''' are performed.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Keyword:JSON&diff=917Keyword:JSON2018-03-22T10:22:59Z<p>Michael Fleming: </p>
<hr />
<div><br />
{{big|'''JSON'''}}<br><br />
<br />
----<br />
<br />
Introduced in version 4.0, this keyword causes <tt>FISPACT-II</tt> to produce an additional output file<br />
<br />
<fileroot>.json<br />
<br />
which is in a JSON format. This allows users to easily parse the outputs using standard packages in many languages.<br />
<br />
For more details on the sections of the legacy output that are supported in the JSON output, see Section 5.6 of the version 4.0 user manual.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Keyword:JSON&diff=916Keyword:JSON2018-03-22T10:09:30Z<p>Michael Fleming: Created page with "{{big|'''JSON'''}}<br> ---- Introduced in version 4.0, this keyword causes <tt>FISPACT-II</tt> to produce an additional output file <fileroot>.json which is in a JSON for..."</p>
<hr />
<div>{{big|'''JSON'''}}<br><br />
<br />
----<br />
<br />
Introduced in version 4.0, this keyword causes <tt>FISPACT-II</tt> to produce an additional output file<br />
<br />
<fileroot>.json<br />
<br />
which is in a JSON format. This allows users to easily parse the outputs using standard packages in many languages.<br />
<br />
For more details on the sections of the legacy output that are supported in the JSON output, see Section 5.6 of the version 4.0 user manual.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Probability_table_self-shielding&diff=915Probability table self-shielding2018-03-20T15:10:56Z<p>Michael Fleming: </p>
<hr />
<div>Self-shielding is an essential aspect of calculating reaction rates which can have very strong effects on numerous observables from criticality to activation. There are two general types of self-shielding which are often classified as energy and spatial self shielding. Methods for correcting reaction rates for both of these self-shielding issues have been implemented within FISPACT-II.<br />
<br />
The essential feature of energy self shielding is that cross sections often contain resonances which are defined for very specific energy regions, which often have large contributions toward the total reaction rate. The large resonance will cause a depression in the neutron population around that energy which may not be reflected in simulations where this feedback is not fully taken into account. It is particularly problematic where cross sections and particle spectra are discretised into some multi-group where the depression in the population for a specific energy cannot be resolved.<br />
<br />
Spatial self-shielding deals with the fact that neutron flux and local spectra can be significantly changed over short distances. In cases with strong resonances, the change in the particle spectrum over short distances can be very large in the region around the resonance.<br />
<br />
<br />
=Methods=<br />
<br />
FISPACT-II employs probability tables generated by CALENDF-2010 to offer material and dilution specific reaction rates. Probability tables are provided for macro-partial cross sections including elastic scattering, absorption, fission, inelastic scattering and neutron production (excluding fission). An infinite dilution cross section is calculated based on the raw spectrum and cross sections, which may be expanded in Gauss quatratures:<br />
<br />
<math><br />
\sigma(x,d=\infty)=\frac{1}{E_{max}-E_{min}}\int_{E_{min}}^{E_{max}} \sigma(E)\, dE= \sum_{n=1}^N P(x,n) \sigma(x,n)<br />
</math><br />
<br />
The cross sections σ and probility tables P are dependent upon the parent nuclide <math>p</math>, energy group <math>g</math>, macro-partial index <math>x</math> and quadrature index <math>n</math>. When a nuclide is a constituent of a homogeneous mixture, the effective cross sections in the resonance regsions are reduced and cna be parameterised using the dilution:<br />
<br />
Dilutions are calculated based on the material composition and an iterative algorithm using the library cross section values. These dilutions are used to recalculate the cross sections for each macro-partial. Two different approaches which are available through the [[Keyword:PROBTABLE | '''PROBTABLE''']] keyword, are to scale the reaction rates base don the total cross section or macro-partials, which also initiates different dilution algorithms. For more details see the models appendix of the user manual.<br />
<br />
The self-shielding factors are applied through the use of either [[Keyword:SSFFUEL | '''SSFFUEL''']] (which uses isotopic definitions just as the [[Keyword:FUEL | '''FUEL''']] keyword) or [[Keyword:SSFMASS | '''SSFMASS''']] (which employs natural elements by mass %). Specific dilution values may be overwritten by hand using the [[Keyword:SSFDILUTION | '''SSFDILUTION''']] keyword. More details on the use of these functionalities can be found in the inputs section of the manual.<br />
<br />
<br />
=Application example=</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Getting_started_examples&diff=914Getting started examples2018-03-20T15:10:35Z<p>Michael Fleming: </p>
<hr />
<div>The FISPACT-II [http://www.ccfe.ac.uk/FISPACT-II/documentation/UKAEA-R18001.pdf user manual] contains a detailed 'getting started' section with numerous example simulations. These are included in the installation media within the /getting_started/ directory. A short overview is provided here which mirrors that section. <br />
<br />
FISPACT-II can perform many types of simulations, but the most common is composed of four stages:<br />
<br />
* Process the library data<br />
** Collapse the cross-section data with incident particle spectra<br />
** Condense the decay and fission yield data<br />
** Print summary of library and simulation-specific collapsed data<br />
<br />
* Set the initial conditions<br />
<br />
* Run irradiation (heating) phase(s)<br />
<br />
* Run cooling phase(s)<br />
<br />
While these can be performed with one input, it is illustrative to separate out components. As a first example, we suggest walking through a simulation of an irradiation of Inconel performed at the JAEA Fusion Neutron Source. After this first example, there are more example simulations which are distributed with the official FISPACT-II release. These are described in their own pages below: <br />
<br />
[[Getting started: first example]]<br />
<br />
[[Getting started: using different nuclear data]]<br />
<br />
[[Getting started: fission decay heat pulse]]<br />
<br />
[[Getting started: reactor power simulation]]<br />
<br />
[[Getting started: solver convergence]]</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=913Main Page2018-03-20T15:09:08Z<p>Michael Fleming: </p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform serves as an online resource for code users which draws heavily from the [http://www.ccfe.ac.uk/FISPACT-II/documentation/UKAEA-R18001.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [https://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2017, ENDF/B.VIII.0, JENDL-4.0 and JEFF-3.3 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Supported systems]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
*[[Docker images]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub]<br />
* [https://github.com/fispact/ FISPACT-II GitHub]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:aquamarine;width:10%;" | 4.0<br />
| style="width:10%;" | Feb 2018<br />
| This release includes code extensions to handle high-energy (MF=10) nuclear data forms including the HEIR and HEAD libraries, the addition of non-neutron covariances for uncertainty propagation, addition of triton- and helion-induced simulation, new JSON output formats and various bug-fixes. The code now has regression testing, with automated builds tested on more than 100 operating system versions. The base Docker images used for tests can be found on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker hub]. Reference outputs for these systems can be found on the system_tests folder. All new nuclear data libraries, including TENDL-2017, JEFF-3.3 and ENDF/B-VIII were processed and tested with this new version. A new python package [https://github.com/fispact/pypact pypact] for output parsing was also released. <br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=912Main Page2018-02-05T17:37:43Z<p>Michael Fleming: </p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform, set up in 2016, serves as an online resource for code users which draws heavily from the [http://fispact.ukaea.uk/wp-content/uploads/2016/06/UKAEA-R1111.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [https://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2017, ENDF/B.VIII, JENDL-4.0 and JEFF-3.3 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Supported systems]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
*[[Docker images]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub]<br />
* [https://github.com/fispact/ FISPACT-II GitHub]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:aquamarine;width:10%;" | 4.0<br />
| style="width:10%;" | Jan 2018<br />
| This release includes code extensions to handle high-energy (MF=10) nuclear data forms including the HEIR and HEAD libraries, the addition of non-neutron covariances for uncertainty propagation, addition of triton- and helion-induced simulation, new JSON output formats and various bug-fixes. The code now has regression testing, with automated builds tested on more than 100 operating system versions. The base Docker images used for tests can be found on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker hub]. Reference outputs for these systems can be found on the system_tests folder. All new nuclear data libraries, including TENDL-2017, JEFF-3.3 and ENDF/B-VIII were processed and tested with this new version. A new python package [https://github.com/fispact/pypact pypact] for output parsing was also released. <br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Supported_systems&diff=911Supported systems2018-02-05T13:59:45Z<p>Michael Fleming: </p>
<hr />
<div>From FISPACT-II version 4.0, the code is tested using Docker containers on over 100 operating system versions, based on compiled binaries on a [[Docker images | set of standard systems]]. The code is compiled with the Intel® Fortran Compiler 18.0 and GNU Fortran compilers with versions ranging from 5.3.1 to 7.2. Users are advised to use one of the provided binaries from the tested systems, typically with a preference for an Intel® Fortran version where available.<br />
<br />
{| class="wikitable sortable"<br />
|+ Operating systems tested with FISPACT-II, using default Docker images (left) and the binaries compiled on various systems with different compilers (right).<br />
! System<br />
! Version<br />
! Tested binaries<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| latest<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| xenial<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 16.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| trusty<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 14.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| devel<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| bionic<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 18.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| rolling<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| artful<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| zesty<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 17.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 17.10<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 12.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| latest<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| edge<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.7<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.6<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.5<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.4<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.3<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.2<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.1<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 2.7<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 2.6<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| latest<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| leap<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| tumbleweed<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| 42.3<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| 42.2<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| 42.1<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| latest<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6.9<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6.8<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6.7<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6.6<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.0.1406<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.1.1503<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.2.1511<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.3.1611<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.4.1708<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| latest<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| rawhide<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 27<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 26<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 25<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 24<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 23<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 22<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 21<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| latest<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| rc-buggy<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| experimental<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 7-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 7.11-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| wheezy-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| wheezy-backports<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 7<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 7.11<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| wheezy<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| unstable-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| testing-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| testing<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 9-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 9.3-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| stretch<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| stretch-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 9<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 9.3<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| stable<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| sid<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| sid-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| oldstable<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| oldstable-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 8<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 8-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 8.10-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 8.10<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| jessie<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| latest<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 18.0<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 18.1<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 18.2<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 18<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 17.3<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 17<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| latest<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.4<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.3<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.2<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.1<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.0<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7-slim<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6.7<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6.8<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6.9<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6-slim<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/scientificlinux ScientificLinux]<br />
| latest<br />
| ScientificLinux-6:Intel-2018 ScientificLinux-6:GNU-6 ScientificLinux-7:Intel-2018 ScientificLinux-7:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/scientificlinux ScientificLinux]<br />
| 7<br />
| ScientificLinux-6:Intel-2018 ScientificLinux-6:GNU-6 ScientificLinux-7:Intel-2018 ScientificLinux-7:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/scientificlinux ScientificLinux]<br />
| 6<br />
| ScientificLinux-6:Intel-2018 ScientificLinux-6:GNU-6</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Supplied_QA_inputs/outputs&diff=910Supplied QA inputs/outputs2018-02-01T14:16:57Z<p>Michael Fleming: </p>
<hr />
<div><br />
== Version 4.0 ==<br />
<br />
As of FISPACT-II version 4.0, the code is tested using a continuous-integration framework on a suite of [[Docker images]]. These utilise a set of test cases drawn the FISPACT-II <tt>system_tests</tt>. The inputs for these are provided with the code and are [http://ccfe.ac.uk/FISPACT-II/Release-4.0/system_tests.tar.bz2 available to download]. Descriptions for all of the tests are provided in the table below. <br />
<br />
Note that outputs with the new JSON format are provided in a separate test case for those indicated, and that the ''core'' operating systems (Ubuntu 16.04, macOS 10.12 and Windows 10) are tested on all, while a subset are used on the remaining [[Docker images | operating systems]]. <br />
<br />
<br />
{| class="wikitable sortable" <br />
|+ System tests provided in FISPACT-II release 4.0<br />
! Test folder<br />
! JSON<br />
! Core systems<br />
! All systems<br />
! ENDF-6<br />
! EAF<br />
! Description<br />
|-<br />
| Tst_162alph<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 alpha irradiation<br />
|-<br />
| Tst_162deut<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 deuteron irradiation<br />
|-<br />
| Tst_162gamm<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 gamma irradiation<br />
|-<br />
| Tst_162prot<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 proton irradiation<br />
|-<br />
| Tst_709fns<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 simulations of D-T neutron irradiation from FNS decay heat experiments<br />
|-<br />
| Tst_709lib<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Comparison of fission calculations using ENDF/B-VII.1, TENDL-2017. JEFF-3.2 and JENDL-4.0<br />
|-<br />
| Tst_709mc<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Monte-Carlo sensitivity-uncertainty calculations<br />
|-<br />
| Tst_709pt<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 probability table self-shielding examples<br />
|-<br />
| Tst_709uc<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDNl-2017 geometry self-shielding examples using universal sigmoid model<br />
|-<br />
| Tst_conv<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Spectrum conversion into group structures matching nuclear data libraries<br />
|-<br />
| Tst_ggs<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Example calculations with different gamma group structures for decay spectra<br />
|-<br />
| Tst_mat<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Fusion wall loading example with nucgraph plots<br />
|-<br />
| Tst_multispec<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Multiple irradiation steps with updated spectra for different steps<br />
|-<br />
| Tst_nfy<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Energy-dependent fission yield handling with the GEFY fission yield library<br />
|-<br />
| Tst_162trit<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 triton (H3) irradiation<br />
|-<br />
| Tst_162heli<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 helion (He3) irradiation<br />
|-<br />
| Tst_prot_he<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| 1 GeV simulation splicing TENDL-2017 and HEIR-0.1 residual product library data<br />
|-<br />
| Tst_066<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 66 group data<br />
|-<br />
| Tst_069<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 69 group data<br />
|-<br />
| Tst_100<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 100 group data<br />
|-<br />
| Tst_172v<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 172 group (fission micro-flux weighting) data<br />
|-<br />
| Tst_172w<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 172 group (fusion micro-flux weighting) data<br />
|-<br />
| Tst_175<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 175 group data<br />
|-<br />
| Tst_211<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 211 group data<br />
|-<br />
| Tst_315<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 315 group data<br />
|-<br />
| Tst_351<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 351 group data<br />
|-<br />
| Tst_616<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 616 (LANL) group data<br />
|-<br />
| Tst_616pt<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 616 (LANL) group data and probability table self-shielding<br />
|-<br />
| Tst_burn<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 69 group data and multiple spectra during burn-up steps<br />
|-<br />
| Tst_deut<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using EAF deuteron-induced reaction data<br />
|-<br />
| Tst_prot<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using EAF proton-induced reaction data<br />
|-<br />
| Tst_spec<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using spectrum convert into 172 group (fission micro-flux weighting) data<br />
|}<br />
<br />
== Versions 3.0 - 3.20 ==<br />
<br />
Supplied with Version 3.00 of the FISPACT-II software are 185 test input files in the <tt>fispQA2010</tt> directory and 324 test input files in the <tt>fispQA</tt> directory together with test output and log files to illustrate the running of FISPACT-II for a variety of irradiation and cooling scenarios, using all the di erent EAF and ENDF library files and illustrating the use of all the [[FISPACT-II keywords]].<br />
<br />
The <tt>fispQA</tt> test set provides tests that use the now default ENDF format libraries introduced in Version 2 for cross sections, fission yields and decay, and the new CALENDF output files for the probability tables used in calculating self-shielding. It is<br />
recommended that you use these libraries rather than the older EAF format libraries as they provide you with better and more extensive nuclear data. The usage of the keywords for the two libraries is almost identical, and if you find an example using nthe EAF libraries then you can easily translate it into an example using the ENDF libraries following the procedure outlined in [[Converting legacy inputs | converting legacy inputs]].<br />
<br />
'''Note that some of the test cases issue warnings and some terminate with fatal error messages. The purpose of these test cases is to illustrate the nerrors that are issued if obsolescent keywords are used, or if keywords are used incorrectly in the input file.'''<br />
<br />
While the [[Getting started examples | getting started examples]] give several introductory simulations and the descriptions provided in the [[FISPACT-II keywords | keyword pages]] give technical descriptions for the required parameters, working examples of each keyword may be found by simple <tt>grep</tt> probing of the QA folders. For example, a search for uncertainty calculations within the <tt>fispQA2010</tt> would return:<br />
<br />
.../fispQA2010> grep UNCER Tst_*/*.i<br />
Tst_162deut/test33.i:UNCERT 3<br />
Tst_162deut/test34.i:UNCERT 3<br />
Tst_162prot/test3.i:UNCERT 3<br />
...<br />
Tst_709fis/test117.i:UNCERT 2<br />
Tst_709fis/test118.i:UNCERT 2<br />
Tst_709fns/Ag.i:UNCERT 2<br />
...<br />
<br />
Reference calculations are provided in the QA folders (''again not that some demonstrate errors and error logging'') which can be checked by hand or through tools such as <tt>diff</tt>. It is recommended that new installations be checked by automatic running of the QA suite using the provided scripts. For more description see the [[Installing FISPACT-II | installing FISPACT-II]] section.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Supplied_QA_inputs/outputs&diff=909Supplied QA inputs/outputs2018-02-01T14:15:31Z<p>Michael Fleming: /* Version 4.0 */</p>
<hr />
<div><br />
== Version 4.0 ==<br />
<br />
As of FISPACT-II version 4.0, the code is tested using a continuous-integration framework on a suite of [[Docker images]]. These utilise a set of test cases drawn the FISPACT-II <tt>system_tests</tt>. The inputs for these are provided with the code and are [http://ccfe.ac.uk/FISPACT-II/Release-4.0/system_tests.tar.bz2 available to download]. Descriptions for all of the tests are provided in the table below. <br />
<br />
Note that outputs with the new JSON format are provided in a separate test case for those indicated, and that the ''core'' operating systems (Ubuntu-16.04, macOS 10.12 and Windows10) are tested on all, while a subset are used on the remaining [[Docker images | operating systems]]. <br />
<br />
<br />
{| class="wikitable sortable" <br />
|+ System tests provided in FISPACT-II release 4.0<br />
! Test folder<br />
! JSON<br />
! Core systems<br />
! All systems<br />
! ENDF-6<br />
! EAF<br />
! Description<br />
|-<br />
| Tst_162alph<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 alpha irradiation<br />
|-<br />
| Tst_162deut<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 deuteron irradiation<br />
|-<br />
| Tst_162gamm<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 gamma irradiation<br />
|-<br />
| Tst_162prot<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 proton irradiation<br />
|-<br />
| Tst_709fns<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 simulations of D-T neutron irradiation from FNS decay heat experiments<br />
|-<br />
| Tst_709lib<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Comparison of fission calculations using ENDF/B-VII.1, TENDL-2017. JEFF-3.2 and JENDL-4.0<br />
|-<br />
| Tst_709mc<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Monte-Carlo sensitivity-uncertainty calculations<br />
|-<br />
| Tst_709pt<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 probability table self-shielding examples<br />
|-<br />
| Tst_709uc<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDNl-2017 geometry self-shielding examples using universal sigmoid model<br />
|-<br />
| Tst_conv<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Spectrum conversion into group structures matching nuclear data libraries<br />
|-<br />
| Tst_ggs<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Example calculations with different gamma group structures for decay spectra<br />
|-<br />
| Tst_mat<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Fusion wall loading example with nucgraph plots<br />
|-<br />
| Tst_multispec<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Multiple irradiation steps with updated spectra for different steps<br />
|-<br />
| Tst_nfy<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Energy-dependent fission yield handling with the GEFY fission yield library<br />
|-<br />
| Tst_162trit<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 triton (H3) irradiation<br />
|-<br />
| Tst_162heli<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 helion (He3) irradiation<br />
|-<br />
| Tst_prot_he<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| 1 GeV simulation splicing TENDL-2017 and HEIR-0.1 residual product library data<br />
|-<br />
| Tst_066<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 66 group data<br />
|-<br />
| Tst_069<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 69 group data<br />
|-<br />
| Tst_100<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 100 group data<br />
|-<br />
| Tst_172v<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 172 group (fission micro-flux weighting) data<br />
|-<br />
| Tst_172w<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 172 group (fusion micro-flux weighting) data<br />
|-<br />
| Tst_175<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 175 group data<br />
|-<br />
| Tst_211<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 211 group data<br />
|-<br />
| Tst_315<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 315 group data<br />
|-<br />
| Tst_351<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 351 group data<br />
|-<br />
| Tst_616<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 616 (LANL) group data<br />
|-<br />
| Tst_616pt<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 616 (LANL) group data and probability table self-shielding<br />
|-<br />
| Tst_burn<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 69 group data and multiple spectra during burn-up steps<br />
|-<br />
| Tst_deut<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using EAF deuteron-induced reaction data<br />
|-<br />
| Tst_prot<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using EAF proton-induced reaction data<br />
|-<br />
| Tst_spec<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using spectrum convert into 172 group (fission micro-flux weighting) data<br />
|}<br />
<br />
== Versions 3.0 - 3.20 ==<br />
<br />
Supplied with Version 3.00 of the FISPACT-II software are 185 test input files in the <tt>fispQA2010</tt> directory and 324 test input files in the <tt>fispQA</tt> directory together with test output and log files to illustrate the running of FISPACT-II for a variety of irradiation and cooling scenarios, using all the di erent EAF and ENDF library files and illustrating the use of all the [[FISPACT-II keywords]].<br />
<br />
The <tt>fispQA</tt> test set provides tests that use the now default ENDF format libraries introduced in Version 2 for cross sections, fission yields and decay, and the new CALENDF output files for the probability tables used in calculating self-shielding. It is<br />
recommended that you use these libraries rather than the older EAF format libraries as they provide you with better and more extensive nuclear data. The usage of the keywords for the two libraries is almost identical, and if you find an example using nthe EAF libraries then you can easily translate it into an example using the ENDF libraries following the procedure outlined in [[Converting legacy inputs | converting legacy inputs]].<br />
<br />
'''Note that some of the test cases issue warnings and some terminate with fatal error messages. The purpose of these test cases is to illustrate the nerrors that are issued if obsolescent keywords are used, or if keywords are used incorrectly in the input file.'''<br />
<br />
While the [[Getting started examples | getting started examples]] give several introductory simulations and the descriptions provided in the [[FISPACT-II keywords | keyword pages]] give technical descriptions for the required parameters, working examples of each keyword may be found by simple <tt>grep</tt> probing of the QA folders. For example, a search for uncertainty calculations within the <tt>fispQA2010</tt> would return:<br />
<br />
.../fispQA2010> grep UNCER Tst_*/*.i<br />
Tst_162deut/test33.i:UNCERT 3<br />
Tst_162deut/test34.i:UNCERT 3<br />
Tst_162prot/test3.i:UNCERT 3<br />
...<br />
Tst_709fis/test117.i:UNCERT 2<br />
Tst_709fis/test118.i:UNCERT 2<br />
Tst_709fns/Ag.i:UNCERT 2<br />
...<br />
<br />
Reference calculations are provided in the QA folders (''again not that some demonstrate errors and error logging'') which can be checked by hand or through tools such as <tt>diff</tt>. It is recommended that new installations be checked by automatic running of the QA suite using the provided scripts. For more description see the [[Installing FISPACT-II | installing FISPACT-II]] section.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Supplied_QA_inputs/outputs&diff=908Supplied QA inputs/outputs2018-02-01T14:10:31Z<p>Michael Fleming: </p>
<hr />
<div><br />
== Version 4.0 ==<br />
<br />
<br />
{| class="wikitable sortable" <br />
|+ System tests provided in FISPACT-II release 4.0<br />
! Test folder<br />
! JSON<br />
! Core systems<br />
! All systems<br />
! ENDF-6<br />
! EAF<br />
! Description<br />
|-<br />
| Tst_162alph<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 alpha irradiation<br />
|-<br />
| Tst_162deut<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 deuteron irradiation<br />
|-<br />
| Tst_162gamm<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 gamma irradiation<br />
|-<br />
| Tst_162prot<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 proton irradiation<br />
|-<br />
| Tst_709fns<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 simulations of D-T neutron irradiation from FNS decay heat experiments<br />
|-<br />
| Tst_709lib<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Comparison of fission calculations using ENDF/B-VII.1, TENDL-2017. JEFF-3.2 and JENDL-4.0<br />
|-<br />
| Tst_709mc<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Monte-Carlo sensitivity-uncertainty calculations<br />
|-<br />
| Tst_709pt<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 probability table self-shielding examples<br />
|-<br />
| Tst_709uc<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDNl-2017 geometry self-shielding examples using universal sigmoid model<br />
|-<br />
| Tst_conv<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Spectrum conversion into group structures matching nuclear data libraries<br />
|-<br />
| Tst_ggs<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Example calculations with different gamma group structures for decay spectra<br />
|-<br />
| Tst_mat<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Fusion wall loading example with nucgraph plots<br />
|-<br />
| Tst_multispec<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Multiple irradiation steps with updated spectra for different steps<br />
|-<br />
| Tst_nfy<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Energy-dependent fission yield handling with the GEFY fission yield library<br />
|-<br />
| Tst_162trit<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 triton (H3) irradiation<br />
|-<br />
| Tst_162heli<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 helion (He3) irradiation<br />
|-<br />
| Tst_prot_he<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| 1 GeV simulation splicing TENDL-2017 and HEIR-0.1 residual product library data<br />
|-<br />
| Tst_066<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 66 group data<br />
|-<br />
| Tst_069<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 69 group data<br />
|-<br />
| Tst_100<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 100 group data<br />
|-<br />
| Tst_172v<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 172 group (fission micro-flux weighting) data<br />
|-<br />
| Tst_172w<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 172 group (fusion micro-flux weighting) data<br />
|-<br />
| Tst_175<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 175 group data<br />
|-<br />
| Tst_211<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 211 group data<br />
|-<br />
| Tst_315<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 315 group data<br />
|-<br />
| Tst_351<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 351 group data<br />
|-<br />
| Tst_616<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 616 (LANL) group data<br />
|-<br />
| Tst_616pt<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 616 (LANL) group data and probability table self-shielding<br />
|-<br />
| Tst_burn<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 69 group data and multiple spectra during burn-up steps<br />
|-<br />
| Tst_deut<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using EAF deuteron-induced reaction data<br />
|-<br />
| Tst_prot<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using EAF proton-induced reaction data<br />
|-<br />
| Tst_spec<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using spectrum convert into 172 group (fission micro-flux weighting) data<br />
|}<br />
<br />
<br />
== Versions 3.0 - 3.20 ==<br />
<br />
Supplied with Version 3.00 of the FISPACT-II software are 185 test input files in the <tt>fispQA2010</tt> directory and 324 test input files in the <tt>fispQA</tt> directory together with test output and log files to illustrate the running of FISPACT-II for a variety of irradiation and cooling scenarios, using all the di erent EAF and ENDF library files and illustrating the use of all the [[FISPACT-II keywords]].<br />
<br />
The <tt>fispQA</tt> test set provides tests that use the now default ENDF format libraries introduced in Version 2 for cross sections, fission yields and decay, and the new CALENDF output files for the probability tables used in calculating self-shielding. It is<br />
recommended that you use these libraries rather than the older EAF format libraries as they provide you with better and more extensive nuclear data. The usage of the keywords for the two libraries is almost identical, and if you find an example using nthe EAF libraries then you can easily translate it into an example using the ENDF libraries following the procedure outlined in [[Converting legacy inputs | converting legacy inputs]].<br />
<br />
'''Note that some of the test cases issue warnings and some terminate with fatal error messages. The purpose of these test cases is to illustrate the nerrors that are issued if obsolescent keywords are used, or if keywords are used incorrectly in the input file.'''<br />
<br />
While the [[Getting started examples | getting started examples]] give several introductory simulations and the descriptions provided in the [[FISPACT-II keywords | keyword pages]] give technical descriptions for the required parameters, working examples of each keyword may be found by simple <tt>grep</tt> probing of the QA folders. For example, a search for uncertainty calculations within the <tt>fispQA2010</tt> would return:<br />
<br />
.../fispQA2010> grep UNCER Tst_*/*.i<br />
Tst_162deut/test33.i:UNCERT 3<br />
Tst_162deut/test34.i:UNCERT 3<br />
Tst_162prot/test3.i:UNCERT 3<br />
...<br />
Tst_709fis/test117.i:UNCERT 2<br />
Tst_709fis/test118.i:UNCERT 2<br />
Tst_709fns/Ag.i:UNCERT 2<br />
...<br />
<br />
Reference calculations are provided in the QA folders (''again not that some demonstrate errors and error logging'') which can be checked by hand or through tools such as <tt>diff</tt>. It is recommended that new installations be checked by automatic running of the QA suite using the provided scripts. For more description see the [[Installing FISPACT-II | installing FISPACT-II]] section.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Supplied_QA_inputs/outputs&diff=907Supplied QA inputs/outputs2018-02-01T14:08:22Z<p>Michael Fleming: Added summary table for v 4.0 system_tests</p>
<hr />
<div>Supplied with Version 3.00 of the FISPACT-II software are 185 test input files in the <tt>fispQA2010</tt> directory and 324 test input files in the <tt>fispQA</tt> directory together with test output and log files to illustrate the running of FISPACT-II for a variety of irradiation and cooling scenarios, using all the di erent EAF and ENDF library files and illustrating the use of all the [[FISPACT-II keywords]].<br />
<br />
The <tt>fispQA</tt> test set provides tests that use the now default ENDF format libraries introduced in Version 2 for cross sections, fission yields and decay, and the new CALENDF output files for the probability tables used in calculating self-shielding. It is<br />
recommended that you use these libraries rather than the older EAF format libraries as they provide you with better and more extensive nuclear data. The usage of the keywords for the two libraries is almost identical, and if you find an example using nthe EAF libraries then you can easily translate it into an example using the ENDF libraries following the procedure outlined in [[Converting legacy inputs | converting legacy inputs]].<br />
<br />
'''Note that some of the test cases issue warnings and some terminate with fatal error messages. The purpose of these test cases is to illustrate the nerrors that are issued if obsolescent keywords are used, or if keywords are used incorrectly in the input file.'''<br />
<br />
While the [[Getting started examples | getting started examples]] give several introductory simulations and the descriptions provided in the [[FISPACT-II keywords | keyword pages]] give technical descriptions for the required parameters, working examples of each keyword may be found by simple <tt>grep</tt> probing of the QA folders. For example, a search for uncertainty calculations within the <tt>fispQA2010</tt> would return:<br />
<br />
.../fispQA2010> grep UNCER Tst_*/*.i<br />
Tst_162deut/test33.i:UNCERT 3<br />
Tst_162deut/test34.i:UNCERT 3<br />
Tst_162prot/test3.i:UNCERT 3<br />
...<br />
Tst_709fis/test117.i:UNCERT 2<br />
Tst_709fis/test118.i:UNCERT 2<br />
Tst_709fns/Ag.i:UNCERT 2<br />
...<br />
<br />
Reference calculations are provided in the QA folders (''again not that some demonstrate errors and error logging'') which can be checked by hand or through tools such as <tt>diff</tt>. It is recommended that new installations be checked by automatic running of the QA suite using the provided scripts. For more description see the [[Installing FISPACT-II | installing FISPACT-II]] section.<br />
<br />
{| class="wikitable sortable" <br />
|+ System tests provided in FISPACT-II release 4.0<br />
! Test folder<br />
! JSON<br />
! Core systems<br />
! All systems<br />
! ENDF-6<br />
! EAF<br />
! Description<br />
|-<br />
| Tst_162alph<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 alpha irradiation<br />
|-<br />
| Tst_162deut<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 deuteron irradiation<br />
|-<br />
| Tst_162gamm<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 gamma irradiation<br />
|-<br />
| Tst_162prot<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 proton irradiation<br />
|-<br />
| Tst_709fns<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 simulations of D-T neutron irradiation from FNS decay heat experiments<br />
|-<br />
| Tst_709lib<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Comparison of fission calculations using ENDF/B-VII.1, TENDL-2017. JEFF-3.2 and JENDL-4.0<br />
|-<br />
| Tst_709mc<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Monte-Carlo sensitivity-uncertainty calculations<br />
|-<br />
| Tst_709pt<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 probability table self-shielding examples<br />
|-<br />
| Tst_709uc<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDNl-2017 geometry self-shielding examples using universal sigmoid model<br />
|-<br />
| Tst_conv<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Spectrum conversion into group structures matching nuclear data libraries<br />
|-<br />
| Tst_ggs<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Example calculations with different gamma group structures for decay spectra<br />
|-<br />
| Tst_mat<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Fusion wall loading example with nucgraph plots<br />
|-<br />
| Tst_multispec<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
| Multiple irradiation steps with updated spectra for different steps<br />
|-<br />
| Tst_nfy<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| Energy-dependent fission yield handling with the GEFY fission yield library<br />
|-<br />
| Tst_162trit<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 triton (H3) irradiation<br />
|-<br />
| Tst_162heli<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| TENDL-2017 helion (He3) irradiation<br />
|-<br />
| Tst_prot_he<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
| 1 GeV simulation splicing TENDL-2017 and HEIR-0.1 residual product library data<br />
|-<br />
| Tst_066<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 66 group data<br />
|-<br />
| Tst_069<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 69 group data<br />
|-<br />
| Tst_100<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 100 group data<br />
|-<br />
| Tst_172v<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 172 group (fission micro-flux weighting) data<br />
|-<br />
| Tst_172w<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 172 group (fusion micro-flux weighting) data<br />
|-<br />
| Tst_175<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 175 group data<br />
|-<br />
| Tst_211<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 211 group data<br />
|-<br />
| Tst_315<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 315 group data<br />
|-<br />
| Tst_351<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 351 group data<br />
|-<br />
| Tst_616<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 616 (LANL) group data<br />
|-<br />
| Tst_616pt<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 616 (LANL) group data and probability table self-shielding<br />
|-<br />
| Tst_burn<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using 69 group data and multiple spectra during burn-up steps<br />
|-<br />
| Tst_deut<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using EAF deuteron-induced reaction data<br />
|-<br />
| Tst_prot<br />
|<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using EAF proton-induced reaction data<br />
|-<br />
| Tst_spec<br />
|<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
|<br />
|style="text-align: center;" | ✓ <br />
| EAF calculations using spectrum convert into 172 group (fission micro-flux weighting) data</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Supported_systems&diff=906Supported systems2018-02-01T11:14:44Z<p>Michael Fleming: Created page with "From FISPACT-II version 4.0, the code is tested using Docker containers on over 100 operating system versions, based on compiled binaries on a Docker images | set of standar..."</p>
<hr />
<div>From FISPACT-II version 4.0, the code is tested using Docker containers on over 100 operating system versions, based on compiled binaries on a [[Docker images | set of standard systems]]. The code is compiled with the Intel® Fortran Compiler 18.0 and GNU Fortran compilers with versions ranging from 5.3.1 to 7.2. Users are advised to use one of the provided binaries from the tested systems, typically with a preference for an Intel® Fortran version where available.<br />
<br />
{| class="wikitable sortable"<br />
|+ Operating systems tested with FISPACT-II, using default Docker images (left) and the binaries compiled on various systems with different compilers (right).<br />
! System<br />
! Version<br />
! Tested binaries<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| latest<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| xenial<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 16.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| trusty<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 14.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| devel<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| bionic<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 18.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| rolling<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| artful<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| zesty<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 17.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 17.10<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/ubuntu Ubuntu]<br />
| 12.04<br />
| Ubuntu-16.04:Intel-2018 Ubuntu-16.04:GNU-5 Ubuntu-16.04:GNU-7 Ubuntu-17.10:Intel-2018 Ubuntu-17.10:GNU-7 Ubuntu-18.04:Intel-2018 Ubuntu-18.04:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| latest<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| edge<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.7<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.6<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.5<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.4<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.3<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.2<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 3.1<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 2.7<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/alpine Alpine]<br />
| 2.6<br />
| Alpine-3.6:Intel-2018 Alpine-3.6:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| latest<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| leap<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| tumbleweed<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| 42.3<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| 42.2<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/opensuse openSUSE]<br />
| 42.1<br />
| openSUSE-42.3:Intel-2018 openSUSE-42.3:GNU-5 openSUSE-42.3:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| latest<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6.9<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6.8<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6.7<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 6.6<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.0.1406<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.1.1503<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.2.1511<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.3.1611<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/centos CentOS]<br />
| 7.4.1708<br />
| CentOS-6.9:Intel-2018 CentOS-6.9:GNU-6 CentOS-7.4:Intel-2018 CentOS-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| latest<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| rawhide<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 27<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 26<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 25<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 24<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 23<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 22<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/fedora Fedora]<br />
| 21<br />
| Fedora-26:Intel-2018 Fedora-26:GNU-7 Fedora-27:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| latest<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| rc-buggy<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| experimental<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 7-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 7.11-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| wheezy-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| wheezy-backports<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 7<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 7.11<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| wheezy<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| unstable-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| testing-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| testing<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 9-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 9.3-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| stretch<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| stretch-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 9<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 9.3<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| stable<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| sid<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| sid-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| oldstable<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| oldstable-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 8<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 8-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 8.10-slim<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| 8.10<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/debian Debian]<br />
| jessie<br />
| Debian-9:Intel-2018 Debian-9:GNU-7<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| latest<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 18.0<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 18.1<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 18.2<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 18<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 17.3<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/linuxmint LinuxMint]<br />
| 17<br />
| LinuxMint-18:Intel-2018 LinuxMint-18:GNU-5<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| latest<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.4<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.3<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.2<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.1<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7.0<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 7-slim<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6 OracleLinux-7.4:Intel-2018 OracleLinux-7.4:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6.7<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6.8<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6.9<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/oraclelinux OracleLinux]<br />
| 6-slim<br />
| OracleLinux-6.9:Intel-2018 OracleLinux-6.9:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/scientificlinux ScientificLinux]<br />
| latest<br />
| ScientificLinux-6:Intel-2018 ScientificLinux-6:GNU-6 ScientificLinux-7:Intel-2018 ScientificLinux-7:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/scientificlinux ScientificLinux]<br />
| 7<br />
| ScientificLinux-6:Intel-2018 ScientificLinux-6:GNU-6 ScientificLinux-7:Intel-2018 ScientificLinux-7:GNU-6<br />
|-<br />
| [https://hub.docker.com/_/scientificlinux ScientificLinux]<br />
| 6<br />
| ScientificLinux-6:Intel-2018 ScientificLinux-6:GNU-6</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Docker_images&diff=905Docker images2018-02-01T09:44:17Z<p>Michael Fleming: </p>
<hr />
<div>From version 4.0 (2018), FISPACT-II is automatically built and tested using [https://www.docker.com/what-docker Docker containers]. This allows the code to be rigorously tested on multiple (over 100) [[Supported systems | operating systems/versions]] and with different compilers - all within a continuous integration framework and without manual intervention.<br />
<br />
FISPACT-II has been built and tested on all of the images available on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub], with regression tests performed using those tagged with <tt>_data</tt>. The suite of [[Supplied QA inputs/outputs | system test inputs/outputs]] have been drawn from these automated regression tests and users can verify results from their own system against reference results from the suite.<br />
<br />
{| class="wikitable sortable" <br />
|+ Docker images used in FISPACT-II testing<br />
! System<br />
! Version<br />
! Compiler<br />
! colspan="2" | Docker<br />
! colspan="2" | Build<br />
! colspan="2" | Github<br />
! Data<br />
|-<br />
| Ubuntu<br />
| 16.04<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:16.04_gfortran_5]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/image/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| rowspan="4" | https://img.shields.io/docker/pulls/fispact/ubuntu.svg<br />
| rowspan="4" | [https://hub.docker.com/r/fispact/ubuntu/builds/ https://img.shields.io/docker/build/fispact/ubuntu.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/16.04_gfortran_5 fispact/docker_ubuntu:16.04_gfortran_5]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/commit/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Ubuntu<br />
| 16.04<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:16.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/16.04_gfortran_7 fispact/docker_ubuntu:16.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Ubuntu<br />
| 18.04<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:18.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:18.04_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/18.04_gfortran_7 fispact/docker_ubuntu:18.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:18.04_gfortran_7.svg]<br />
|<br />
|-<br />
| Ubuntu<br />
| 17.10<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:17.10_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:17.10_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/17.10_gfortran_7 fispact/docker_ubuntu:17.10_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:17.10_gfortran_7.svg]<br />
|<br />
|-<br />
| openSUSE<br />
| 42.3<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/opensuse/ fispact/opensuse:42.3_gfortran_5]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/image/fispact/opensuse:42.3_gfortran_5.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/opensuse.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/opensuse/builds/ https://img.shields.io/docker/build/fispact/opensuse.svg]<br />
| [https://github.com/fispact/docker_opensuse/tree/42.3_gfortran_5 fispact/docker_opensuse:42.3_gfortran_5]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/commit/fispact/opensuse:42.3_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| openSUSE<br />
| 42.3<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/opensuse/ fispact/opensuse:42.3_gfortran_7]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/image/fispact/opensuse:42.3_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_opensuse/tree/42.3_gfortran_7 fispact/docker_opensuse:42.3_gfortran_7]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/commit/fispact/opensuse:42.3_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| CentOS<br />
| 7.4<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/centos/ fispact/centos:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/image/fispact/centos:7.4_gfortran_6.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/centos.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/centos/builds/ https://img.shields.io/docker/build/fispact/centos.svg]<br />
| [https://github.com/fispact/docker_centos/tree/7.4_gfortran_6 fispact/docker_centos:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/commit/fispact/centos:7.4_gfortran_6.svg]<br />
|<br />
|-<br />
| CentOS<br />
| 6.9<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/centos/ fispact/centos:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/image/fispact/centos:6.9_gfortran_6.svg]<br />
| [https://github.com/fispact/docker_centos/tree/6.9_gfortran_6 fispact/docker_centos:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/commit/fispact/centos:6.9_gfortran_6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Fedora<br />
| 27<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/fedora/ fispact/fedora:27_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/image/fispact/fedora:27_gfortran_7.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/fedora.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/fedora/builds/ https://img.shields.io/docker/build/fispact/fedora.svg]<br />
| [https://github.com/fispact/docker_fedora/tree/27_gfortran_7 fispact/docker_fedora:27_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/commit/fispact/fedora:27_gfortran_7.svg]<br />
|<br />
|-<br />
| Fedora<br />
| 26<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/fedora/ fispact/fedora:26_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/image/fispact/fedora:26_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_fedora/tree/26_gfortran_7 fispact/docker_fedora:26_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/commit/fispact/fedora:26_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| LinuxMint<br />
| 18<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/linuxmint/ fispact/linuxmint:18_gfortran_5]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/image/fispact/linuxmint:18_gfortran_5.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/linuxmint.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/linuxmint/builds/ https://img.shields.io/docker/build/fispact/linuxmint.svg]<br />
| [https://github.com/fispact/docker_linuxmint/tree/18_gfortran_5 fispact/docker_linuxmint:18_gfortran_5]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/commit/fispact/linuxmint:18_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Debian<br />
| 9<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/debian/ fispact/debian:9_gfortran_7]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/image/fispact/debian:9_gfortran_7.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/debian.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/debian/builds/ https://img.shields.io/docker/build/fispact/debian.svg]<br />
| [https://github.com/fispact/docker_debian/tree/9_gfortran_7 fispact/docker_debian:9_gfortran_7]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/commit/fispact/debian:9_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Alpine<br />
| 3.6<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/alpine/ fispact/alpine:3.6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/image/fispact/alpine:3.6_gfortran_6.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/alpine.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/alpine/builds/ https://img.shields.io/docker/build/fispact/alpine.svg]<br />
| [https://github.com/fispact/docker_alpine/tree/3.6_gfortran_6 fispact/docker_alpine:3.6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/commit/fispact/alpine:3.6_gfortran_6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| ArchLinux<br />
| latest<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/archlinux/ fispact/archlinux:latest]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/image/fispact/archlinux:latest.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/archlinux.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/archlinux/builds/ https://img.shields.io/docker/build/fispact/archlinux.svg]<br />
| [https://github.com/fispact/docker_archlinux fispact/docker_archlinux:latest]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/commit/fispact/archlinux:latest.svg]<br />
|<br />
|-<br />
| ScientificLinux<br />
| 6<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/scientificlinux/ fispact/scientificlinux:6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6_gfortran_6 https://images.microbadger.com/badges/image/fispact/scientificlinux:6_gfortran_6.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/scientificlinux.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/scientificlinux/builds/ https://img.shields.io/docker/build/fispact/scientificlinux.svg]<br />
| [https://github.com/fispact/docker_scientificlinux/tree/6 fispact/docker_scientificlinux:6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6 https://images.microbadger.com/badges/commit/fispact/scientificlinux:6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| ScientificLinux<br />
| 7<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/scientificlinux/ fispact/scientificlinux:7_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7_gfortran_6 https://images.microbadger.com/badges/image/fispact/scientificlinux:7_gfortran_6.svg]<br />
| [https://github.com/fispact/docker_scientificlinux/tree/7 fispact/docker_scientificlinux:7_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7 https://images.microbadger.com/badges/commit/fispact/scientificlinux:7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| OracleLinux<br />
| 7.4<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/oraclelinux/ fispact/oraclelinux:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4_gfortran_6 https://images.microbadger.com/badges/image/fispact/oraclelinux:7.4_gfortran_6.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/oraclelinux.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/oraclelinux/builds/ https://img.shields.io/docker/build/fispact/oraclelinux.svg]<br />
| [https://github.com/fispact/docker_oraclelinux/tree/7.4 fispact/docker_oraclelinux:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4 https://images.microbadger.com/badges/commit/fispact/oraclelinux:7.4.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| OracleLinux<br />
| 6.9<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/oraclelinux/ fispact/oraclelinux:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/image/fispact/oraclelinux:6.9.svg]<br />
| [https://github.com/fispact/docker_oraclelinux/tree/6.9 fispact/docker_oraclelinux:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/commit/fispact/oraclelinux:6.9.svg]<br />
| style="text-align: center;" | ✓</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=904Main Page2018-02-01T09:43:37Z<p>Michael Fleming: /* Getting started */</p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform, set up in 2016, serves as an online resource for code users which draws heavily from the [http://fispact.ukaea.uk/wp-content/uploads/2016/06/UKAEA-R1111.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [http://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2017, ENDF/B.VIII, JENDL-4.0 and JEFF-3.3 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Supported systems]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
*[[Docker images]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub]<br />
* [https://github.com/fispact/ FISPACT-II GitHub]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:aquamarine;width:10%;" | 4.0<br />
| style="width:10%;" | Jan 2018<br />
| This release includes code extensions to handle high-energy (MF=10) nuclear data forms including the HEIR and HEAD libraries, the addition of non-neutron covariances for uncertainty propagation, addition of triton- and helion-induced simulation, new JSON output formats and various bug-fixes. The code now has regression testing, with automated builds tested on more than 100 operating system versions. The base Docker images used for tests can be found on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker hub]. Reference outputs for these systems can be found on the system_tests folder. All new nuclear data libraries, including TENDL-2017, JEFF-3.3 and ENDF/B-VIII were processed and tested with this new version. A new python package [https://github.com/fispact/pypact pypact] for output parsing was also released. <br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=FISPACT-II_keywords&diff=903FISPACT-II keywords2018-01-30T17:58:20Z<p>Michael Fleming: </p>
<hr />
<div>A run of FISPACT-II is controlled by a sequence of commands given in a user-supplied input file, the anatomy of which is described in the [[Code execution overview | code execution page]]. This requires a series of keywords to be specified for control, initial and inventory stages. Below are all of the keywords available in the most recent release of FISPACT-II, sorted by their phase and with a short description. Pages for each of the keywords are linked from this table which provide details of how to use each. Please note that as the code develops new keywords are added to allow access to new features while retaining backwards compatibility. For clarity, keywords added or modified since the 3-00-00 distribution are identified with the scheme below.<br />
<br />
{|class="wikitable"<br />
| style="background:Aquamarine;"|<br />
| Release 4.0+<br />
| style="background:#a0e75a;"|<br />
| Release 3-20-00+<br />
| style="background:Khaki;"|<br />
| Release 3-00-00+<br />
|}<br />
<br />
{| class="wikitable sortable" <br />
|+ FISPACT-II Keywords<br />
! Keyword<br />
! Version<br />
! Control<br />
! Initial<br />
! Invent.<br />
! Description<br />
|-<br />
| [[Keyword:ALLDISPEN | ALLDISPEN]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Sets the displacement energies (in eV) for all nuclides<br />
|-<br />
| [[Keyword:ATDISPEN | ATDISPEN]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Sets the displacement energies (in eV) for specified elements<br />
|-<br />
| [[Keyword:ATOMS | ATOMS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Sets initial conditions and initiates output with inventories and observables. After the [[Keyword:ZERO | ZERO]] keyword will also output uncertainties<br />
|-<br />
| [[Keyword:ATWO | ATWO]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes output of legal limits for activity in transport of radioactive material<br />
|-<br />
| [[Keyword:BREMSSTRAHLUNG | BREMSSTRAHLUNG]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes output of brehmsstrahlung contributions for specified nuclides<br />
|-<br />
| [[Keyword:CLEAR | CLEAR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes clearance data of radionuclides to be output<br />
|-<br />
| [[Keyword:CLOBBER | CLOBBER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows FISPACT-II to overwrite existing output with same name<br />
|-<br />
| [[Keyword:CNVTYPE | CNVTYPE]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the user to specify formalism for conversion of incident particle spectra<br />
|-<br />
| [[Keyword:COVARIANCE | COVARIANCE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes cross-channel covariances to be calculated (if present in nuclear data)<br />
|-<br />
| [[Keyword:CULTAB | CULTAB]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Produces additional lines in tab files for specific post-processing tools<br />
|-<br />
| [[Keyword:CUMFYLD | CUMFYLD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the cumulative fission yields to be read, rather than the default independent yields<br />
<br />
|-<br />
| [[Keyword:DENSITY | DENSITY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specifies a density of the material in grams per cubic centimetre<br />
|-<br />
| [[Keyword:DEPLETION | DEPLETION]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes FISPACT-II to output the uncertainty from all depletion processes for a set of specified nuclides<br />
|-<br />
| [[Keyword:DOSE | DOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows modification of the dose rate values from semi-infinite slab to point sources<br />
|-<br />
| [[Keyword:END | END]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Terminates the input of the simulation<br />
|-<br />
| [[Keyword:ENDPULSE | ENDPULSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Terminates the [[Keyword:PULSE | PULSE]] phase in the simulation<br />
|-<br />
| [[Keyword:ERROR | ERROR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows manual override of error values for uncertainty quantification<br />
|-<br />
| [[Keyword:FISCHOOSE | FISCHOOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to select actinides for pathways-based uncertainty - note that this does not affect the use of fission in the inventory simulation<br />
|-<br />
| [[Keyword:FISPACT | FISPACT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| A divider keyword which separates the library data preparation, initialising that process before subsequent actions<br />
|-<br />
| [[Keyword:FISYIELD | FISYIELD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to specify which fission yields are read and included in the inventory simulation<br />
|-<br />
| [[Keyword:FLUX | FLUX]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Used to specify an incident particle flux in particles per square centimetre per second<br />
|-<br />
| [[Keyword:FUEL | FUEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specification of initial inventory by nuclide, rather than by element (which is done using [[Keyword:MASS | MASS]])<br />
|-<br />
| [[Keyword:FULLXS | FULLXS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the full, energy-dependent group cross sections to be stored when the library is being collapsed<br />
|-<br />
| [[Keyword:GENERIC | GENERIC]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Produces generic pathways data removing isomeric transitions<br />
|-<br />
| [[Keyword:GETDECAY | GETDECAY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the condense of decay data or reading of a pre-compiled binary file<br />
|-<br />
| [[Keyword:GETXS | GETXS]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Initiates the collapse of an incident particle spectrum with the cross sections to generate one-group values. Now with the ability to use arbirtary (ebins) incident group structure<br />
|-<br />
| [[Keyword:GRAPH | GRAPH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the output of summarised graph files and plotting scripts in a variety of possible formats<br />
|-<br />
| [[Keyword:GROUP | GROUP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the specification of an output gamma group structure<br />
|-<br />
| [[Keyword:GRPCONVERT | GRPCONVERT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the conversion of an incident spectrum from one multi group to another<br />
|-<br />
| [[Keyword:HALF | HALF]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes half-lives of all nuclides to be output at each step<br />
|-<br />
| [[Keyword:HAZARDS | HAZARDS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Reads in ingestion/inhalation doses and outputs contributions from all nuclides at all steps<br />
|-<br />
| [[Keyword:INDEXPATH | INDEXPATH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes index of nuclides significant pathways to be written out<br />
|-<br />
| [[Keyword:IRON | IRON]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Special keyword for low-impurity iron simulation, to remove iron responses and allow high-accuracy impurity analyses<br />
|-<br />
| [[Keyword:JSON | JSON]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Keyword causes the output of a new JSON file in versions 4.0+<br />
|-<br />
| [[Keyword:LIBVERSION | LIBVERSION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Controls input data format, allowing legacy EAF data to be used<br />
|-<br />
| [[Keyword:LIMGRP | LIMGRP]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Clips the incident particle spectrum at minimum and/or maximum energies, summing into the lowest and/or highest groups<br />
|-<br />
| [[Keyword:LOGLEVEL | LOGLEVEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Controls the sophistication of the logging outputs, particularly useful for error identification<br />
|-<br />
| [[Keyword:LOOKAHEAD | LOOKAHEAD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Fine-tunes pathway analyses by searching for long-lived nuclides and including them in post-irradiation dominant lists<br />
|-<br />
| [[Keyword:MASS | MASS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Input inventory specification by element, instead of by nuclide (as done with the [[Keyword:FUEL | FUEL]] keyword)<br />
|-<br />
| [[Keyword:MCSAMPLE | MCSAMPLE]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Used in conjunction with [[Keyword:SENSITIVITY | SENSITIVITY]] to change the Monte-Carlo sampling of nuclear data uncertainties. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:MCSEED | MCSEED]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows specification of random number seeds in Monte-Carlo sensitivity calculations<br />
|-<br />
| [[Keyword:MIND | MIND]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Sets a minimum number of nuclides to follow in the simualation<br />
|-<br />
| [[Keyword:MONITOR | MONITOR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Controls whether or not FISPACT-II will output a description of the execution steps to the terminal<br />
|-<br />
| [[Keyword:NOCOMP | NOCOMP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the elemental composition table to be omitted from the output<br />
|-<br />
| [[Keyword:NOERROR | NOERROR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Turns off uncertainty from nuclear data files, although manual inclusion of error can be done using [[Keyword:ERROR | ERROR]]<br />
|-<br />
| [[Keyword:NOFISS | NOFISS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Stops the use of fission yield data from being processed and then used in the simulation<br />
|-<br />
| [[Keyword:NOSORT | NOSORT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Removes the output of dominant nuclides and subsequent pathways/uncertainty data<br />
|-<br />
| [[Keyword:NOSTABLE | NOSTABLE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Removes stable nuclides from the output files<br />
|-<br />
| [[Keyword:NOT1 | NOT1]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB1 | TAB1]]<br />
|-<br />
| [[Keyword:NOT2 | NOT2]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB2 | TAB2]]<br />
|-<br />
| [[Keyword:NOT3 | NOT3]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB3 | TAB3]]<br />
|-<br />
| [[Keyword:NOT4 | NOT4]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB4 | TAB4]]<br />
|-<br />
| [[Keyword:NUCGRAPH | NUCGRAPH]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| <br />
| style="text-align: center;" | ✓<br />
| <br />
| Creates data outputs and plot scripts with break-downs for all individual dominant nuclides (as opposed to integral quantities)<br />
|-<br />
| [[Keyword:OVER | OVER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the manual overriding of cross sections, half-lives and their errors<br />
|-<br />
| [[Keyword:PARTITION | PARTITION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Allows the partitioning of the inventory by element, making multiple parallel simulations<br />
|-<br />
| [[Keyword:PATH | PATH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specifies a specific pathway which will be included in the pathways analysis<br />
|-<br />
| [[Keyword:PATHRESET | PATHRESET]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Initiates a new pathways search and uncertainty quantification at the post-irradiation step that it is called in<br />
|-<br />
| [[Keyword:POWER | POWER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the incident particle flux to be renormalised to match a specified volumetric power, using full kerma values from the nuclear data<br />
|-<br />
| [[Keyword:PRINTLIB | PRINTLIB]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the printing of a range of library data, check the keyword options for more guidance<br />
|-<br />
| [[Keyword:PROBTABLE | PROBTABLE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Specifies the method of application of self-shielding factors<br />
|-<br />
| [[Keyword:PROJECTILE | PROJECTILE]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Selects the incident particle used in the simulations, for example neutron or one of the four other charged particles currently allowed. As of version 4.0, two additional options have been added for triton- and helion- induced reaction data<br />
|-<br />
| [[Keyword:PULSE | PULSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Initiates a set of repeated irradiation steps with given flux and duration, must be ended with [[Keyword:ENDPULSE | ENDPULSE]]<br />
|-<br />
| [[Keyword:READGG | READGG]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the user to specify an output gamma group structure for decay sources<br />
|-<br />
| [[Keyword:READSF | READSF]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the reading and use of spontaneous fission yield data<br />
|-<br />
| [[Keyword:RESULT | RESULT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Outputs the total number of atoms tracked in pathways analyses for the specified nuclides<br />
|-<br />
| [[Keyword:ROUTES | ROUTES]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| A method for specifying a range of pathways between two nuclides for inclusion in the pathways analyses<br />
|-<br />
| [[Keyword:SAVELINES | SAVELINES]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes spectral lines from the decay data to be stored and can be further printed using the [[Keyword:PRINTLIB | PRINTLIB 5]] option<br />
|-<br />
| [[Keyword:SENSITIVITY | SENSITIVITY]]<br />
| style="white-space:nowrap;background:Khaki;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes sensitivity calculations to be performed over a specified set of nuclides and reactions. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:SORTDOMINANT | SORTDOMINANT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Controls the number of nuclides to blue included in the dominant lists and used in uncertainty quantification<br />
|-<br />
| [[Keyword:SPECTRUM | SPECTRUM]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Alternative to [[Keyword:ATOMS | ATOMS]] which suppresses the full inventory output and gives the gamma spectrum<br />
|-<br />
| [[Keyword:SPEK | SPEK]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes calculation of an approximate gamma spectrum for nuclides which have no spectral data<br />
|-<br />
| [[Keyword:SPLIT | SPLIT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the display of additional gamma and beta heat data in the final summary table<br />
|-<br />
| [[Keyword:SSFCHOOSE | SSFCHOOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Selects the set of nuclides for which self-shielding factors will be applied<br />
|-<br />
| [[Keyword:SSFDILUTION | SSFDILUTION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows manual override of dilution values for self-shielding factor calculation in a group-by-group basis<br />
|-<br />
| [[Keyword:SSFFUEL | SSFFUEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the specification of inventory to be used in the calculation of dilutions and self-shielding factors by nuclide (instead of by element, as with [[Keyword:SSFMASS | SSFMASS]])<br />
|-<br />
| [[Keyword:SSFGEOMETRY | SSFGEOMETRY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Provides spatial self-shielding using the universal sigmoid curve for foils, wires, spheres and cylinders<br />
|-<br />
| [[Keyword:SSFMASS | SSFMASS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the specification of inventory to be used in the calculation of dilutions and self-shielding factors by element (instead of by nuclide, as with [[Keyword:SSFFUEL | SSFFUEL]])<br />
|-<br />
| [[Keyword:STEP | STEP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Performs the same function of [[Keyword:ATOMS | ATOMS]] but suppresses the output data <br />
|-<br />
| [[Keyword:TAB1 | TAB1]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the inventory data (atoms and mass) to a two column TAB1 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB2 | TAB2]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the activity and dose rate from each nuclide to a two column TAB2 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB3 | TAB3]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the ingestion and inhalation dose from each nuclide to a two column TAB3 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB4 | TAB4]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes a multi-group gamma spectrum to a TAB4 file<br />
|-<br />
| [[Keyword:TIME | TIME]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Sets the time-steps in the simulation and triggers the processing of any keyword actions that have been queued<br />
|-<br />
| [[Keyword:TOLERANCE | TOLERANCE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the modification of solver tolerance values<br />
|-<br />
| [[Keyword:UNCERTAINTY | UNCERTAINTY]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the code to perform pathways-based uncertainty quantification and allows manual control of algorithm parameters. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:UNCTYPE | UNCTYPE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to specify the uncertainties used in the simulation, including cross sections and/or half-lives<br />
|-<br />
| [[Keyword:USEFISSION | USEFISSION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes fission yields to be included in the inventory matrix<br />
|-<br />
| [[Keyword:USESPALLATION | USESPALLATION]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the <tt>sp_endf</tt> and <tt>xs_endf</tt> files for specified nuclides to be spliced at a user-supplied energy and recorded in the <tt>xs_extra</tt> directory before being used in subsequent simulation<br />
|-<br />
| [[Keyword:USEXSEXTRA | USEXSEXTRA]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
|<br />
|<br />
| Causes <tt>xsextra</tt> folder, typically generated using [[Keyword:USESPALLATION | USESPALLATION]], files to be preferentially utilised instead of those within the group cross section library<br />
|-<br />
| [[Keyword:WALL | WALL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the input of a neutron first wall loading in surface power, which will renormalise the incident particle flux<br />
|-<br />
| [[Keyword:XSTHRESHOLD | XSTHRESHOLD]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
|<br />
| Controls the treshold minimum cross section for inclusion required for inclusion in the calculation<br />
|-<br />
| [[Keyword:ZERO | ZERO]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Resets the time and moves the simulation into the cooling phase, initiates pathways analyses, uncertainty calculations and output of [[Keyword:GRAPH | GRAPH]] data</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Reference_input_spectra&diff=902Reference input spectra2018-01-30T15:56:40Z<p>Michael Fleming: </p>
<hr />
<div>__NOTOC__<br />
<br />
The collapsed cross-sections depend strongly on the nature of the projectile spectra, and so it is important to use the appropriate spectrum together with the appropriately-weighted cross-section data. With the advances of modern simulation software and high resolution spectra the user is reminded of the importance of the tails, low or high-energy ones, on the reaction rates.<br />
<br />
The majority of neutron-application spectra stem from light-water assemblies, mock-ups or reactors where the integral responses are strongly, if not solely, influenced by the energy ranges of the fission spectra and thermal maxwellian. Fusion spectra that have been obtained from magnetic confinement (MCF) or inertial confinement fusion (ICF) present typical D-D 2.5 MeV, or D-T 14 MeV peaks sometimes accompanied by a higher-energy tail, but also showing rather different slowing-down profiles. Accelerator-driven beam spectra are important in their role in nuclear data acquisition and materials research, but also for medical therapeutic and diagnostic applications.<br />
<br />
In essence the particle spectrum profile, through the collapsing process, emphasises the energy region of most importance for each application. Transferring data from one application or energy range to another should be done with great care as it can easily lead to misleading and inappropriate numerical results.<br />
<br />
Several incident particle spectra are provided in the table below, mostly including neutron incident spectra but with some charged particle spectra. '''Note''' that these are provided in the original energy group structures as generated by the code(s) that calculated them. These are often ''not'' the same energy group structures as those provided for e.g. the TENDL nuclear data libraries and require a flux conversion using [[Keyword:GRPCONVERT | '''GRPCONVERT''']]. Note that while the group conversion can easily be performed, this cannot add structure when moving to a refined group structure when moving to a more refined multi-group.<br />
<br />
Each of the spectra below is provided in the format of an arbitrary flux <tt>arb_flux</tt> file for reading in the '''GRPCONVERT''' module as well as a figure showing the spectrum in flux per unit lethargy using an arbitrary normalisation. For convenience, all of the <tt>arb_flux</tt> files are available in the table below.<br />
<br />
<br />
{| class="wikitable sortable" <br />
|+ Reference incident particle spectra<br />
! Name<br />
! Group<br />
! Particle<br />
! <tt>arb_flux</tt> file<br />
! Figure<br />
! Description<br />
|-<br />
| Bigten<br />
| 407<br />
| n<br />
| [[Media:407 Bigten.txt]]<br />
| [[Reference_input_spectra#Bigten | Bigten]]<br />
| International Criticality Safety Benchmark Experiment, Bigten<br />
|-<br />
| BWR-MOX-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-0.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-0 | BWR-MOX-Gd-0]]<br />
| BWR MOX fuel with Gd, 0 GWd/THM<br />
|-<br />
| BWR-MOX-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-15.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-15 | BWR-MOX-Gd-15]]<br />
| BWR MOX fuel with Gd, 15 GWd/THM<br />
|-<br />
| BWR-MOX-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-40.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-40 | BWR-MOX-Gd-40]]<br />
| BWR MOX fuel with Gd, 40 GWd/THM<br />
|-<br />
| BWR-RPV<br />
| 198<br />
| n<br />
| [[Media:198 BWR-RPV.txt]]<br />
| [[Reference_input_spectra#BWR-RPV | BWR-RPV]]<br />
| Boiling water reactor, 1/4 Thickness reactor pressure vessel<br />
|-<br />
| BWR-UO2-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-0.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-0 | BWR-UO2-Gd-0]]<br />
| BWR UO2 fuel with Gd, 0 GWd/THM<br />
|-<br />
| BWR-UO2-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-15.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-15 | BWR-UO2-Gd-15]]<br />
| BWR UO2 fuel with Gd, 15 GWd/THM<br />
|-<br />
| BWR-UO2-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-40.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-40 | BWR-UO2-Gd-40]]<br />
| BWR UO2 fuel with Gd, 40 GWd/THM<br />
|-<br />
| CERN-H4IRRAD<br />
| 288<br />
| n<br />
| [[Media:288 CERN-H4IRRAD.txt]]<br />
| [[Reference_input_spectra#CERN-H4IRRAD | CERN-H4IRRAD]]<br />
| CERN H4IRRAD experiment<br />
|-<br />
| Cf252<br />
| 070<br />
| n<br />
| [[Media:070 Cf252.txt]]<br />
| [[Reference_input_spectra#Cf252 | Cf252]]<br />
| Californium-252 spontaneous fission source<br />
|-<br />
| DEMO-HCPB-BP<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-BP.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-BP | DEMO-HCPB-BP]]<br />
| DEMO fusion concept He-cooled pebble bed, backplate<br />
|-<br />
| DEMO-HCPB-FW<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-FW.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-FW | DEMO-HCPB-FW]]<br />
| DEMO fusion concept He-cooled pebble bed, first wall<br />
|-<br />
| DEMO-HCPB-VV<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-VV.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-VV | DEMO-HCPB-VV]]<br />
| DEMO fusion concept He-cooled pebble bed, vacuum vessel<br />
|-<br />
| EBR-2<br />
| 029<br />
| n<br />
| [[Media:029 EBR-2.txt]]<br />
| [[Reference_input_spectra#EBR-2 | EBR-2]]<br />
| Experimental Breeder Reactor spectrum<br />
|-<br />
| Frascati-NG<br />
| 175<br />
| n<br />
| [[Media:175 Frascati-NG.txt]]<br />
| [[Reference_input_spectra#Frascati-NG | Frascati-NG]]<br />
| ENEA Frascati Neutron Generator D-T<br />
|-<br />
| HCLL-FW<br />
| 616<br />
| n<br />
| [[Media:616 HCLL-FW.txt]]<br />
| [[Reference_input_spectra#HCLL-FW | HCLL-FW]]<br />
| D-T fusion reactor He-cooled LiPb, first wall<br />
|-<br />
| HCLL-VV<br />
| 616<br />
| n<br />
| [[Media:616 HCLL-VV.txt]]<br />
| [[Reference_input_spectra#HCLL-VV | HCLL-VV]]<br />
| D-T fusion reactor He-cooled LiPb, vacuum vessel<br />
|-<br />
| HCPB-FW<br />
| 616<br />
| n<br />
| [[Media:616 HCPB-FW.txt]]<br />
| [[Reference_input_spectra#HCPB-FW | HCPB-FW]]<br />
| D-T fusion reactor He-cooled pebble bed, first wall<br />
|-<br />
| HCPB-VV<br />
| 616<br />
| n<br />
| [[Media:616 HCPB-VV.txt]]<br />
| [[Reference_input_spectra#HCPB-VV | HCPB-VV]]<br />
| D-T fusion reactor He-cooled pebble bed, vacuum vessel<br />
|-<br />
| HFIR-highres<br />
| 238<br />
| n<br />
| [[Media:238 HFIR-highres.txt]]<br />
| [[Reference_input_spectra#HFIR-highres | HFIR-highres]]<br />
| Material test reactor, Oak Ridge HFIR midplane<br />
|-<br />
| HFIR-lowres<br />
| 100<br />
| n<br />
| [[Media:100 HFIR-lowres.txt]]<br />
| [[Reference_input_spectra#HFIR-lowres | HFIR-lowres]]<br />
| Material test reactor, Oak Ridge HFIR midplane<br />
|-<br />
| HFIR-VXF3-AD<br />
| 238<br />
| n<br />
| [[Media:238 HFIR-VXF3-AD.txt]]<br />
| [[Reference_input_spectra#HFIR-VXF3-AD | HFIR-VXF3-AD]]<br />
| Material test reactor, Oak Ridge HFIR midplane-VXF3-AD<br />
|-<br />
| HFR-high<br />
| 616<br />
| n<br />
| [[Media:616 HFR-high.txt]]<br />
| [[Reference_input_spectra#HFR-high | HFR-high]]<br />
| Material test reactor, Petten HFR high<br />
|-<br />
| HFR-low<br />
| 616<br />
| n<br />
| [[Media:616 HFR-low.txt]]<br />
| [[Reference_input_spectra#HFR-low | HFR-low]]<br />
| Material test reactor, Petten HFR low<br />
|-<br />
| IFMIF-DLi<br />
| 211<br />
| n<br />
| [[Media:211 IFMIF-DLi.txt]]<br />
| [[Reference_input_spectra#IFMIF-DLi | IFMIF-DLi]]<br />
| IFMIF D-Li neutron source<br />
|-<br />
| ITER-DD<br />
| 175<br />
| n<br />
| [[Media:175 ITER-DD.txt]]<br />
| [[Reference_input_spectra#ITER-DD | ITER-DD]]<br />
| Magnetic confinement fusion, ITER D-D<br />
|-<br />
| ITER-DT<br />
| 175<br />
| n<br />
| [[Media:175 ITER-DT.txt]]<br />
| [[Reference_input_spectra#ITER-DT | ITER-DT]]<br />
| Magnetic confinement fusion, ITER D-T<br />
|-<br />
| JAEA-FNS<br />
| 175<br />
| n<br />
| [[Media:175 JAEA-FNS.txt]]<br />
| [[Reference_input_spectra#JAEA-FNS | JAEA-FNS]]<br />
| JAEA Fusion Neutron Source D-T<br />
|-<br />
| JET-FW<br />
| 100<br />
| n<br />
| [[Media:100 JET-FW.txt]]<br />
| [[Reference_input_spectra#JET-FW | JET-FW]]<br />
| Joint European Torus, first wall vacuum vessel<br />
|-<br />
| LMJ-g<br />
| 161<br />
| γ<br />
| [[Media:161 LMJ-g.txt]]<br />
| [[Reference_input_spectra#LMJ-g | LMJ-g]]<br />
| Laser Mégajoule gamma spectra<br />
|-<br />
| Maxwellians<br />
| 709<br />
| n<br />
| [[Media:709 Maxwellian-1keV.txt | 1 keV]] [[Media:709 Maxwellian-5keV.txt | 5 keV]] [[Media:709 Maxwellian-10keV.txt | 10 keV]] [[Media:709 Maxwellian-30keV.txt | 30 keV]] [[Media:709 Maxwellian-80keV.txt | 80 keV]]<br />
| [[Reference_input_spectra#Maxwellians | Maxwellians]]<br />
| Maxwellian neutron spectra at various temperatures<br />
|-<br />
| NIF-ignition<br />
| 150<br />
| n<br />
| [[Media:150 NIF-ignition.txt]]<br />
| [[Reference_input_spectra#NIF-ignition | NIF-ignition]]<br />
| Inertial confinement fusion, NIF ignited<br />
|-<br />
| Paluel<br />
| 172<br />
| n<br />
| [[Media:172 Paluel.txt]]<br />
| [[Reference_input_spectra#Paluel | Paluel]]<br />
| Paluel light water reactor<br />
|-<br />
| Phenix<br />
| 172<br />
| n<br />
| [[Media:172 Phenix.txt]]<br />
| [[Reference_input_spectra#Phenix | Phenix]]<br />
| Fast breeder reactor, Phénix<br />
|-<br />
| PWR-MOX-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-0.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-0 | PWR-MOX-0]]<br />
| PWR MOX fuel with Gd, 0 GWd/THM<br />
|-<br />
| PWR-MOX-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-15.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-15 | PWR-MOX-15]]<br />
| PWR MOX fuel with Gd, 15 GWd/THM<br />
|-<br />
| PWR-MOX-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-40.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-40 | PWR-MOX-40]]<br />
| PWR MOX fuel with Gd, 40 GWd/THM<br />
|-<br />
| PWR-RPV<br />
| 198<br />
| n<br />
| [[Media:198 PWR-RPV.txt]]<br />
| [[Reference_input_spectra#PWR-RPV | PWR-RPV]]<br />
| Pressurized water reactor, 1/4 Thickness reactor pressure vessel<br />
|-<br />
| PWR-UO2-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-0.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-0 | PWR-UO2-0]]<br />
| PWR UO2 fuel, 0 GWd/THM<br />
|-<br />
| PWR-UO2-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-15.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-15 | PWR-UO2-15]]<br />
| PWR UO2 fuel, 15 GWd/THM<br />
|-<br />
| PWR-UO2-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-40.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-40 | PWR-UO2-40]]<br />
| PWR UO2 fuel, 40 GWd/THM<br />
|-<br />
| PWR-UO2-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-0.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-0 | PWR-UO2-Gd-0]]<br />
| PWR UO2 fuel with Gd, 0 GWd/THM<br />
|-<br />
| PWR-UO2-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-15.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-15 | PWR-UO2-Gd-15]]<br />
| PWR UO2 fuel with Gd, 15 GWd/THM<br />
|-<br />
| PWR-UO2-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-40.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-40 | PWR-UO2-Gd-40]]<br />
| PWR UO2 fuel with Gd, 40 GWd/THM<br />
|-<br />
| Superphenix<br />
| 172<br />
| n<br />
| [[Media:172 Superphenix.txt]]<br />
| [[Reference_input_spectra#Superphenix | Superphenix]]<br />
| Fast breeder reactor, Superphénix<br />
|-<br />
| TUD-NG<br />
| 175<br />
| n<br />
| [[Media:175 TUD-NG.txt]]<br />
| [[Reference_input_spectra#TUD-NG | TUD-NG]]<br />
| TU Dresden fusion neutron source D-T<br />
|-<br />
| WCCB-FW<br />
| 616<br />
| n<br />
| [[Media:616 WCCB-FW.txt]]<br />
| [[Reference_input_spectra#WCCB-FW | WCCB-FW]]<br />
| D-T fusion water-cooled ceramic breeder, first wall<br />
|-<br />
| WCCB-VV<br />
| 616<br />
| n<br />
| [[Media:616 WCCB-VV.txt]]<br />
| [[Reference_input_spectra#WCCB-VV | WCCB-VV]]<br />
| D-T fusion water-cooled ceramic breeder, vacuum vessel<br />
|-<br />
| WCLL-FW<br />
| 616<br />
| n<br />
| [[Media:616 WCLL-FW.txt]]<br />
| [[Reference_input_spectra#WCLL-FW | WCLL-FW]]<br />
| D-T fusion water-cooled LiPb, first wall<br />
|-<br />
| WCLL-VV<br />
| 616<br />
| n<br />
| [[Media:616 WCLL-VV.txt]]<br />
| [[Reference_input_spectra#WCLL-VV | WCLL-VV]]<br />
| D-T fusion water-cooled LiPb, vacuum vessel<br />
|}<br />
<br />
<br />
==Bigten==<br />
<br />
[[File:407 Bigten.png|550px|center|thumb|alt=Spectrum|[[Media:407 Bigten.txt]]]]<br />
<br />
==BWR-MOX-Gd-0==<br />
<br />
[[File:1102 BWR-MOX-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-0.txt]]]]<br />
<br />
==BWR-MOX-Gd-15==<br />
<br />
[[File:1102 BWR-MOX-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-15.txt]]]]<br />
<br />
==BWR-MOX-Gd-40==<br />
<br />
[[File:1102 BWR-MOX-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-40.txt]]]]<br />
<br />
==BWR-RPV==<br />
<br />
[[File:198 BWR-RPV.png|550px|center|thumb|alt=Spectrum|[[Media:198 BWR-RPV.txt]]]]<br />
<br />
==BWR-UO2-Gd-0==<br />
<br />
[[File:1102 BWR-UO2-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-0.txt]]]]<br />
<br />
==BWR-UO2-Gd-15==<br />
<br />
[[File:1102 BWR-UO2-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-15.txt]]]]<br />
<br />
==BWR-UO2-Gd-40==<br />
<br />
[[File:1102 BWR-UO2-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-40.txt]]]]<br />
<br />
==CERN-H4IRRAD==<br />
<br />
[[File:288 CERN-H4IRRAD.png|550px|center|thumb|alt=Spectrum|[[Media:288 CERN-H4IRRAD.txt]]]]<br />
<br />
==Cf252==<br />
<br />
[[File:070 Cf252.png|550px|center|thumb|alt=Spectrum|[[Media:070 Cf252.txt]]]]<br />
<br />
==DEMO-HCPB-BP==<br />
<br />
[[File:616 DEMO-HCPB-BP.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-BP.txt]]]]<br />
<br />
==DEMO-HCPB-FW==<br />
<br />
[[File:616 DEMO-HCPB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-FW.txt]]]]<br />
<br />
==DEMO-HCPB-VV==<br />
<br />
[[File:616 DEMO-HCPB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-VV.txt]]]]<br />
<br />
==EBR-2==<br />
<br />
[[File:029 EBR-2.png|550px|center|thumb|alt=Spectrum|[[Media:029 EBR-2.txt]]]]<br />
<br />
==Frascati-NG==<br />
<br />
[[File:175 Frascati-NG.png|550px|center|thumb|alt=Spectrum|[[Media:175 Frascati-NG.txt]]]]<br />
<br />
==HCLL-FW==<br />
<br />
[[File:616 HCLL-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCLL-FW.txt]]]]<br />
<br />
==HCLL-VV==<br />
<br />
[[File:616 HCLL-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCLL-VV.txt]]]]<br />
<br />
==HCPB-FW==<br />
<br />
[[File:616 HCPB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCPB-FW.txt]]]]<br />
<br />
==HCPB-VV==<br />
<br />
[[File:616 HCPB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCPB-VV.txt]]]]<br />
<br />
==HFIR-highres==<br />
<br />
[[File:238 HFIR-highres.png|550px|center|thumb|alt=Spectrum|[[Media:238 HFIR-highres.txt]]]]<br />
<br />
==HFIR-lowres==<br />
<br />
[[File:100 HFIR-lowres.png|550px|center|thumb|alt=Spectrum|[[Media:100 HFIR-lowres.txt]]]]<br />
<br />
==HFIR-VXF3-AD==<br />
<br />
[[File:238 HFIR-VXF3-AD.png|550px|center|thumb|alt=Spectrum|[[Media:238 HFIR-VXF3-AD.txt]]]]<br />
<br />
==HFR-high==<br />
<br />
[[File:616 HFR-high.png|550px|center|thumb|alt=Spectrum|[[Media:616 HFR-high.txt]]]]<br />
<br />
==HFR-low==<br />
<br />
[[File:616 HFR-low.png|550px|center|thumb|alt=Spectrum|[[Media:616 HFR-low.txt]]]]<br />
<br />
==IFMIF-DLi==<br />
<br />
[[File:211 IFMIF-DLi.png|550px|center|thumb|alt=Spectrum|[[Media:211 IFMIF-DLi.txt]]]]<br />
<br />
==ITER-DD==<br />
<br />
[[File:175 ITER-DD.png|550px|center|thumb|alt=Spectrum|[[Media:175 ITER-DD.txt]]]]<br />
<br />
==ITER-DT==<br />
<br />
[[File:175 ITER-DT.png|550px|center|thumb|alt=Spectrum|[[Media:175 ITER-DT.txt]]]]<br />
<br />
==JAEA-FNS==<br />
<br />
[[File:175 JAEA-FNS.png|550px|center|thumb|alt=Spectrum|[[Media:175 JAEA-FNS.txt]]]]<br />
<br />
==JET-FW==<br />
<br />
[[File:100 JET-FW.png|550px|center|thumb|alt=Spectrum|[[Media:100 JET-FW.txt]]]]<br />
<br />
==LMJ-g==<br />
<br />
[[File:161 LMJ-g.png|550px|center|thumb|alt=Spectrum|[[Media:161 LMJ-g.txt]]]]<br />
<br />
==Maxwellians==<br />
<br />
[[File:709 Maxwellian.png|550px|center|thumb|alt=Spectrum|[[Media:709 Maxwellian-1keV.txt | 1 keV]] [[Media:709 Maxwellian-5keV.txt | 5 keV]] [[Media:709 Maxwellian-10keV.txt | 10 keV]] [[Media:709 Maxwellian-30keV.txt | 30 keV]] [[Media:709 Maxwellian-80keV.txt | 80 keV]]]]<br />
<br />
==NIF-ignition==<br />
<br />
[[File:150 NIF-ignition.png|550px|center|thumb|alt=Spectrum|[[Media:150 NIF-ignition.txt]]]]<br />
<br />
==Paluel==<br />
<br />
[[File:172 Paluel.png|550px|center|thumb|alt=Spectrum|[[Media:172 Paluel.txt]]]]<br />
<br />
==Phenix==<br />
<br />
[[File:172 Phenix.png|550px|center|thumb|alt=Spectrum|[[Media:172 Phenix.txt]]]]<br />
<br />
==PWR-MOX-0==<br />
<br />
[[File:1102 PWR-MOX-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-0.txt]]]]<br />
<br />
==PWR-MOX-15==<br />
<br />
[[File:1102 PWR-MOX-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-15.txt]]]]<br />
<br />
==PWR-MOX-40==<br />
<br />
[[File:1102 PWR-MOX-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-40.txt]]]]<br />
<br />
==PWR-RPV==<br />
<br />
[[File:198 PWR-RPV.png|550px|center|thumb|alt=Spectrum|[[Media:198 PWR-RPV.txt]]]]<br />
<br />
==PWR-UO2-0==<br />
<br />
[[File:1102 PWR-UO2-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-0.txt]]]]<br />
<br />
==PWR-UO2-15==<br />
<br />
[[File:1102 PWR-UO2-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-15.txt]]]]<br />
<br />
==PWR-UO2-40==<br />
<br />
[[File:1102 PWR-UO2-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-40.txt]]]]<br />
<br />
==PWR-UO2-Gd-0==<br />
<br />
[[File:1102 PWR-UO2-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-0.txt]]]]<br />
<br />
==PWR-UO2-Gd-15==<br />
<br />
[[File:1102 PWR-UO2-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-15.txt]]]]<br />
<br />
==PWR-UO2-Gd-40==<br />
<br />
[[File:1102 PWR-UO2-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-40.txt]]]]<br />
<br />
==Superphenix==<br />
<br />
[[File:172 Superphenix.png|550px|center|thumb|alt=Spectrum|[[Media:172 Superphenix.txt]]]]<br />
<br />
==TUD-NG==<br />
<br />
[[File:175 TUD-NG.png|550px|center|thumb|alt=Spectrum|[[Media:175 TUD-NG.txt]]]]<br />
<br />
==WCCB-FW==<br />
<br />
[[File:616 WCCB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCCB-FW.txt]]]]<br />
<br />
==WCCB-VV==<br />
<br />
[[File:616 WCCB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCCB-VV.txt]]]]<br />
<br />
==WCLL-FW==<br />
<br />
[[File:616 WCLL-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCLL-FW.txt]]]]<br />
<br />
==WCLL-VV==<br />
<br />
[[File:616 WCLL-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCLL-VV.txt]]]]</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=FISPACT-II_keywords&diff=901FISPACT-II keywords2018-01-30T08:27:12Z<p>Michael Fleming: </p>
<hr />
<div>A run of FISPACT-II is controlled by a sequence of commands given in a user-supplied input file, the anatomy of which is described in the [[Code execution overview | code execution page]]. This requires a series of keywords to be specified for control, initial and inventory stages. Below are all of the keywords available in the most recent release of FISPACT-II, sorted by their phase and with a short description. Pages for each of the keywords are linked from this table which provide details of how to use each. Please note that as the code develops new keywords are added to allow access to new features while retaining backwards compatibility. For clarity, keywords added or modified since the 3-00-00 distribution are identified with the scheme below.<br />
<br />
{|class="wikitable"<br />
| style="background:Aquamarine;"|<br />
| Release 4.0+<br />
| style="background:#a0e75a;"|<br />
| Release 3-20-00+<br />
| style="background:Khaki;"|<br />
| Release 3-00-00+<br />
|}<br />
<br />
{| class="wikitable sortable" <br />
|+ FISPACT-II Keywords<br />
! Keyword<br />
! Version<br />
! Control<br />
! Initial<br />
! Invent.<br />
! Description<br />
|-<br />
| [[Keyword:ALLDISPEN | ALLDISPEN]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Sets the displacement energies (in eV) for all nuclides<br />
|-<br />
| [[Keyword:ATDISPEN | ATDISPEN]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Sets the displacement energies (in eV) for specified elements<br />
|-<br />
| [[Keyword:ATOMS | ATOMS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Sets initial conditions and initiates output with inventories and observables. After the [[Keyword:ZERO | ZERO]] keyword will also output uncertainties<br />
|-<br />
| [[Keyword:ATWO | ATWO]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes output of legal limits for activity in transport of radioactive material<br />
|-<br />
| [[Keyword:BREMSSTRAHLUNG | BREMSSTRAHLUNG]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes output of brehmsstrahlung contributions for specified nuclides<br />
|-<br />
| [[Keyword:CLEAR | CLEAR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes clearance data of radionuclides to be output<br />
|-<br />
| [[Keyword:CLOBBER | CLOBBER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows FISPACT-II to overwrite existing output with same name<br />
|-<br />
| [[Keyword:CNVTYPE | CNVTYPE]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the user to specify formalism for conversion of incident particle spectra<br />
|-<br />
| [[Keyword:COVARIANCE | COVARIANCE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes cross-channel covariances to be calculated (if present in nuclear data)<br />
|-<br />
| [[Keyword:CULTAB | CULTAB]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Produces additional lines in tab files for specific post-processing tools<br />
|-<br />
| [[Keyword:CUMFYLD | CUMFYLD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the cumulative fission yields to be read, rather than the default independent yields<br />
<br />
|-<br />
| [[Keyword:DENSITY | DENSITY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specifies a density of the material in grams per cubic centimetre<br />
|-<br />
| [[Keyword:DEPLETION | DEPLETION]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes FISPACT-II to output the uncertainty from all depletion processes for a set of specified nuclides<br />
|-<br />
| [[Keyword:DOSE | DOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows modification of the dose rate values from semi-infinite slab to point sources<br />
|-<br />
| [[Keyword:END | END]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Terminates the input of the simulation<br />
|-<br />
| [[Keyword:ENDPULSE | ENDPULSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Terminates the [[Keyword:PULSE | PULSE]] phase in the simulation<br />
|-<br />
| [[Keyword:ERROR | ERROR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows manual override of error values for uncertainty quantification<br />
|-<br />
| [[Keyword:FISCHOOSE | FISCHOOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to select actinides for pathways-based uncertainty - note that this does not affect the use of fission in the inventory simulation<br />
|-<br />
| [[Keyword:FISPACT | FISPACT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| A divider keyword which separates the library data preparation, initialising that process before subsequent actions<br />
|-<br />
| [[Keyword:FISYIELD | FISYIELD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to specify which fission yields are read and included in the inventory simulation<br />
|-<br />
| [[Keyword:FLUX | FLUX]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Used to specify an incident particle flux in particles per square centimetre per second<br />
|-<br />
| [[Keyword:FUEL | FUEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specification of initial inventory by nuclide, rather than by element (which is done using [[Keyword:MASS | MASS]])<br />
|-<br />
| [[Keyword:FULLXS | FULLXS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the full, energy-dependent group cross sections to be stored when the library is being collapsed<br />
|-<br />
| [[Keyword:GENERIC | GENERIC]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Produces generic pathways data removing isomeric transitions<br />
|-<br />
| [[Keyword:GETDECAY | GETDECAY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the condense of decay data or reading of a pre-compiled binary file<br />
|-<br />
| [[Keyword:GETXS | GETXS]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Initiates the collapse of an incident particle spectrum with the cross sections to generate one-group values. Now with the ability to use arbirtary (ebins) incident group structure<br />
|-<br />
| [[Keyword:GRAPH | GRAPH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the output of summarised graph files and plotting scripts in a variety of possible formats<br />
|-<br />
| [[Keyword:GROUP | GROUP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the specification of an output gamma group structure<br />
|-<br />
| [[Keyword:GRPCONVERT | GRPCONVERT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the conversion of an incident spectrum from one multi group to another<br />
|-<br />
| [[Keyword:HALF | HALF]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes half-lives of all nuclides to be output at each step<br />
|-<br />
| [[Keyword:HAZARDS | HAZARDS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Reads in ingestion/inhalation doses and outputs contributions from all nuclides at all steps<br />
|-<br />
| [[Keyword:INDEXPATH | INDEXPATH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes index of nuclides significant pathways to be written out<br />
|-<br />
| [[Keyword:IRON | IRON]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Special keyword for low-impurity iron simulation, to remove iron responses and allow high-accuracy impurity analyses<br />
|-<br />
| [[Keyword:JSON | JSON]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Keyword causes the output of a new JSON file in versions 4.0+<br />
|-<br />
| [[Keyword:LIBVERSION | LIBVERSION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Controls input data format, allowing legacy EAF data to be used<br />
|-<br />
| [[Keyword:LIMGRP | LIMGRP]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Clips the incident particle spectrum at minimum and/or maximum energies, summing into the lowest and/or highest groups<br />
|-<br />
| [[Keyword:LOGLEVEL | LOGLEVEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Controls the sophistication of the logging outputs, particularly useful for error identification<br />
|-<br />
| [[Keyword:LOOKAHEAD | LOOKAHEAD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Fine-tunes pathway analyses by searching for long-lived nuclides and including them in post-irradiation dominant lists<br />
|-<br />
| [[Keyword:MASS | MASS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Input inventory specification by element, instead of by nuclide (as done with the [[Keyword:FUEL | FUEL]] keyword)<br />
|-<br />
| [[Keyword:MCSAMPLE | MCSAMPLE]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Used in conjunction with [[Keyword:SENSITIVITY | SENSITIVITY]] to change the Monte-Carlo sampling of nuclear data uncertainties. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:MCSEED | MCSEED]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows specification of random number seeds in Monte-Carlo sensitivity calculations<br />
|-<br />
| [[Keyword:MIND | MIND]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Sets a minimum number of nuclides to follow in the simualation<br />
|-<br />
| [[Keyword:MONITOR | MONITOR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Controls whether or not FISPACT-II will output a description of the execution steps to the terminal<br />
|-<br />
| [[Keyword:NOCOMP | NOCOMP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the elemental composition table to be omitted from the output<br />
|-<br />
| [[Keyword:NOERROR | NOERROR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Turns off uncertainty from nuclear data files, although manual inclusion of error can be done using [[Keyword:ERROR | ERROR]]<br />
|-<br />
| [[Keyword:NOFISS | NOFISS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Stops the use of fission yield data from being processed and then used in the simulation<br />
|-<br />
| [[Keyword:NOSORT | NOSORT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Removes the output of dominant nuclides and subsequent pathways/uncertainty data<br />
|-<br />
| [[Keyword:NOSTABLE | NOSTABLE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Removes stable nuclides from the output files<br />
|-<br />
| [[Keyword:NOT1 | NOT1]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB1 | TAB1]]<br />
|-<br />
| [[Keyword:NOT2 | NOT2]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB2 | TAB2]]<br />
|-<br />
| [[Keyword:NOT3 | NOT3]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB3 | TAB3]]<br />
|-<br />
| [[Keyword:NOT4 | NOT4]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB4 | TAB4]]<br />
|-<br />
| [[Keyword:NUCGRAPH | NUCGRAPH]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| <br />
| style="text-align: center;" | ✓<br />
| <br />
| Creates data outputs and plot scripts with break-downs for all individual dominant nuclides (as opposed to integral quantities)<br />
|-<br />
| [[Keyword:OVER | OVER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the manual overriding of cross sections, half-lives and their errors<br />
|-<br />
| [[Keyword:PARTITION | PARTITION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Allows the partitioning of the inventory by element, making multiple parallel simulations<br />
|-<br />
| [[Keyword:PATH | PATH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specifies a specific pathway which will be included in the pathways analysis<br />
|-<br />
| [[Keyword:PATHRESET | PATHRESET]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Initiates a new pathways search and uncertainty quantification at the post-irradiation step that it is called in<br />
|-<br />
| [[Keyword:POWER | POWER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the incident particle flux to be renormalised to match a specified volumetric power, using full kerma values from the nuclear data<br />
|-<br />
| [[Keyword:PRINTLIB | PRINTLIB]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the printing of a range of library data, check the keyword options for more guidance<br />
|-<br />
| [[Keyword:PROBTABLE | PROBTABLE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Specifies the method of application of self-shielding factors<br />
|-<br />
| [[Keyword:PROJECTILE | PROJECTILE]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Selects the incident particle used in the simulations, for example neutron or one of the four other charged particles currently allowed. As of version 4.0, two additional options have been added for triton- and helion- induced reaction data<br />
|-<br />
| [[Keyword:PULSE | PULSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Initiates a set of repeated irradiation steps with given flux and duration, must be ended with [[Keyword:ENDPULSE | ENDPULSE]]<br />
|-<br />
| [[Keyword:READGG | READGG]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the user to specify an output gamma group structure for decay sources<br />
|-<br />
| [[Keyword:READSF | READSF]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the reading and use of spontaneous fission yield data<br />
|-<br />
| [[Keyword:RESULT | RESULT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Outputs the total number of atoms tracked in pathways analyses for the specified nuclides<br />
|-<br />
| [[Keyword:ROUTES | ROUTES]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| A method for specifying a range of pathways between two nuclides for inclusion in the pathways analyses<br />
|-<br />
| [[Keyword:SAVELINES | SAVELINES]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes spectral lines from the decay data to be stored and can be further printed using the [[Keyword:PRINTLIB | PRINTLIB 5]] option<br />
|-<br />
| [[Keyword:SENSITIVITY | SENSITIVITY]]<br />
| style="white-space:nowrap;background:Khaki;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes sensitivity calculations to be performed over a specified set of nuclides and reactions. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:SORTDOMINANT | SORTDOMINANT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Controls the number of nuclides to blue included in the dominant lists and used in uncertainty quantification<br />
|-<br />
| [[Keyword:SPECTRUM | SPECTRUM]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Alternative to [[Keyword:ATOMS | ATOMS]] which suppresses the full inventory output and gives the gamma spectrum<br />
|-<br />
| [[Keyword:SPEK | SPEK]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes calculation of an approximate gamma spectrum for nuclides which have no spectral data<br />
|-<br />
| [[Keyword:SPLIT | SPLIT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the display of additional gamma and beta heat data in the final summary table<br />
|-<br />
| [[Keyword:SSFCHOOSE | SSFCHOOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Selects the set of nuclides for which self-shielding factors will be applied<br />
|-<br />
| [[Keyword:SSFDILUTION | SSFDILUTION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows manual override of dilution values for self-shielding factor calculation in a group-by-group basis<br />
|-<br />
| [[Keyword:SSFFUEL | SSFFUEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the specification of inventory to be used in the calculation of dilutions and self-shielding factors by nuclide (instead of by element, as with [[Keyword:SSFMASS | SSFMASS]])<br />
|-<br />
| [[Keyword:SSFGEOMETRY | SSFGEOMETRY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Provides spatial self-shielding using the universal sigmoid curve for foils, wires, spheres and cylinders<br />
|-<br />
| [[Keyword:SSFMASS | SSFMASS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the specification of inventory to be used in the calculation of dilutions and self-shielding factors by element (instead of by nuclide, as with [[Keyword:SSFFUEL | SSFFUEL]])<br />
|-<br />
| [[Keyword:STEP | STEP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Performs the same function of [[Keyword:ATOMS | ATOMS]] but suppresses the output data <br />
|-<br />
| [[Keyword:TAB1 | TAB1]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the inventory data (atoms and mass) to a two column TAB1 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB2 | TAB2]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the activity and dose rate from each nuclide to a two column TAB2 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB3 | TAB3]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the ingestion and inhalation dose from each nuclide to a two column TAB3 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB4 | TAB4]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes a multi-group gamma spectrum to a TAB4 file<br />
|-<br />
| [[Keyword:TIME | TIME]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Sets the time-steps in the simulation and triggers the processing of any keyword actions that have been queued<br />
|-<br />
| [[Keyword:TOLERANCE | TOLERANCE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the modification of solver tolerance values<br />
|-<br />
| [[Keyword:UNCERTAINTY | UNCERTAINTY]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the code to perform pathways-based uncertainty quantification and allows manual control of algorithm parameters. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:UNCTYPE | UNCTYPE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to specify the uncertainties used in the simulation, including cross sections and/or half-lives<br />
|-<br />
| [[Keyword:USEFISSION | USEFISSION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes fission yields to be included in the inventory matrix<br />
|-<br />
| [[Keyword:USESPALLATION | USESPALLATION]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the <tt>sp_endf</tt> and <tt>xs_endf</tt> files for specified nuclides to be spliced at a user-supplied energy and recorded in the <tt>xs_extra</tt> directory before being used in subsequent simulation<br />
|-<br />
| [[Keyword:WALL | WALL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the input of a neutron first wall loading in surface power, which will renormalise the incident particle flux<br />
|-<br />
| [[Keyword:XSTHRESHOLD | XSTHRESHOLD]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
|<br />
| Controls the treshold minimum cross section for inclusion required for inclusion in the calculation<br />
|-<br />
| [[Keyword:ZERO | ZERO]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Resets the time and moves the simulation into the cooling phase, initiates pathways analyses, uncertainty calculations and output of [[Keyword:GRAPH | GRAPH]] data</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Docker_images&diff=900Docker images2018-01-24T17:50:07Z<p>Michael Fleming: </p>
<hr />
<div>From version 4.0 (2018), FISPACT-II is automatically built and tested using [https://www.docker.com/what-docker Docker containers]. This allows the code to be rigorously tested on multiple (over 100) operating systems/versions and with different compilers - all within a continuous integration framework and without manual intervention.<br />
<br />
FISPACT-II has been built and tested on all of the images available on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub], with regression tests performed using those tagged with <tt>_data</tt>. The suite of [[Supplied QA inputs/outputs | system test inputs/outputs]] have been drawn from these automated regression tests and users can verify results from their own system against reference results from the suite.<br />
<br />
{| class="wikitable sortable" <br />
|+ Docker images used in FISPACT-II testing<br />
! System<br />
! Version<br />
! Compiler<br />
! colspan="2" | Docker<br />
! colspan="2" | Build<br />
! colspan="2" | Github<br />
! Data<br />
|-<br />
| Ubuntu<br />
| 16.04<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:16.04_gfortran_5]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/image/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| rowspan="4" | https://img.shields.io/docker/pulls/fispact/ubuntu.svg<br />
| rowspan="4" | [https://hub.docker.com/r/fispact/ubuntu/builds/ https://img.shields.io/docker/build/fispact/ubuntu.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/16.04_gfortran_5 fispact/docker_ubuntu:16.04_gfortran_5]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/commit/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Ubuntu<br />
| 16.04<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:16.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/16.04_gfortran_7 fispact/docker_ubuntu:16.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Ubuntu<br />
| 18.04<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:18.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:18.04_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/18.04_gfortran_7 fispact/docker_ubuntu:18.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:18.04_gfortran_7.svg]<br />
|<br />
|-<br />
| Ubuntu<br />
| 17.10<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:17.10_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:17.10_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/17.10_gfortran_7 fispact/docker_ubuntu:17.10_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:17.10_gfortran_7.svg]<br />
|<br />
|-<br />
| openSUSE<br />
| 42.3<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/opensuse/ fispact/opensuse:42.3_gfortran_5]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/image/fispact/opensuse:42.3_gfortran_5.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/opensuse.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/opensuse/builds/ https://img.shields.io/docker/build/fispact/opensuse.svg]<br />
| [https://github.com/fispact/docker_opensuse/tree/42.3_gfortran_5 fispact/docker_opensuse:42.3_gfortran_5]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/commit/fispact/opensuse:42.3_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| openSUSE<br />
| 42.3<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/opensuse/ fispact/opensuse:42.3_gfortran_7]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/image/fispact/opensuse:42.3_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_opensuse/tree/42.3_gfortran_7 fispact/docker_opensuse:42.3_gfortran_7]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/commit/fispact/opensuse:42.3_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| CentOS<br />
| 7.4<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/centos/ fispact/centos:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/image/fispact/centos:7.4_gfortran_6.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/centos.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/centos/builds/ https://img.shields.io/docker/build/fispact/centos.svg]<br />
| [https://github.com/fispact/docker_centos/tree/7.4_gfortran_6 fispact/docker_centos:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/commit/fispact/centos:7.4_gfortran_6.svg]<br />
|<br />
|-<br />
| CentOS<br />
| 6.9<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/centos/ fispact/centos:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/image/fispact/centos:6.9_gfortran_6.svg]<br />
| [https://github.com/fispact/docker_centos/tree/6.9_gfortran_6 fispact/docker_centos:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/commit/fispact/centos:6.9_gfortran_6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Fedora<br />
| 27<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/fedora/ fispact/fedora:27_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/image/fispact/fedora:27_gfortran_7.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/fedora.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/fedora/builds/ https://img.shields.io/docker/build/fispact/fedora.svg]<br />
| [https://github.com/fispact/docker_fedora/tree/27_gfortran_7 fispact/docker_fedora:27_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/commit/fispact/fedora:27_gfortran_7.svg]<br />
|<br />
|-<br />
| Fedora<br />
| 26<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/fedora/ fispact/fedora:26_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/image/fispact/fedora:26_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_fedora/tree/26_gfortran_7 fispact/docker_fedora:26_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/commit/fispact/fedora:26_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| LinuxMint<br />
| 18<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/linuxmint/ fispact/linuxmint:18_gfortran_5]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/image/fispact/linuxmint:18_gfortran_5.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/linuxmint.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/linuxmint/builds/ https://img.shields.io/docker/build/fispact/linuxmint.svg]<br />
| [https://github.com/fispact/docker_linuxmint/tree/18_gfortran_5 fispact/docker_linuxmint:18_gfortran_5]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/commit/fispact/linuxmint:18_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Debian<br />
| 9<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/debian/ fispact/debian:9_gfortran_7]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/image/fispact/debian:9_gfortran_7.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/debian.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/debian/builds/ https://img.shields.io/docker/build/fispact/debian.svg]<br />
| [https://github.com/fispact/docker_debian/tree/9_gfortran_7 fispact/docker_debian:9_gfortran_7]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/commit/fispact/debian:9_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Alpine<br />
| 3.6<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/alpine/ fispact/alpine:3.6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/image/fispact/alpine:3.6_gfortran_6.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/alpine.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/alpine/builds/ https://img.shields.io/docker/build/fispact/alpine.svg]<br />
| [https://github.com/fispact/docker_alpine/tree/3.6_gfortran_6 fispact/docker_alpine:3.6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/commit/fispact/alpine:3.6_gfortran_6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| ArchLinux<br />
| latest<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/archlinux/ fispact/archlinux:latest]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/image/fispact/archlinux:latest.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/archlinux.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/archlinux/builds/ https://img.shields.io/docker/build/fispact/archlinux.svg]<br />
| [https://github.com/fispact/docker_archlinux fispact/docker_archlinux:latest]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/commit/fispact/archlinux:latest.svg]<br />
|<br />
|-<br />
| ScientificLinux<br />
| 6<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/scientificlinux/ fispact/scientificlinux:6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6_gfortran_6 https://images.microbadger.com/badges/image/fispact/scientificlinux:6_gfortran_6.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/scientificlinux.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/scientificlinux/builds/ https://img.shields.io/docker/build/fispact/scientificlinux.svg]<br />
| [https://github.com/fispact/docker_scientificlinux/tree/6 fispact/docker_scientificlinux:6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6 https://images.microbadger.com/badges/commit/fispact/scientificlinux:6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| ScientificLinux<br />
| 7<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/scientificlinux/ fispact/scientificlinux:7_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7_gfortran_6 https://images.microbadger.com/badges/image/fispact/scientificlinux:7_gfortran_6.svg]<br />
| [https://github.com/fispact/docker_scientificlinux/tree/7 fispact/docker_scientificlinux:7_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7 https://images.microbadger.com/badges/commit/fispact/scientificlinux:7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| OracleLinux<br />
| 7.4<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/oraclelinux/ fispact/oraclelinux:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4_gfortran_6 https://images.microbadger.com/badges/image/fispact/oraclelinux:7.4_gfortran_6.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/oraclelinux.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/oraclelinux/builds/ https://img.shields.io/docker/build/fispact/oraclelinux.svg]<br />
| [https://github.com/fispact/docker_oraclelinux/tree/7.4 fispact/docker_oraclelinux:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4 https://images.microbadger.com/badges/commit/fispact/oraclelinux:7.4.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| OracleLinux<br />
| 6.9<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/oraclelinux/ fispact/oraclelinux:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/image/fispact/oraclelinux:6.9.svg]<br />
| [https://github.com/fispact/docker_oraclelinux/tree/6.9 fispact/docker_oraclelinux:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/commit/fispact/oraclelinux:6.9.svg]<br />
| style="text-align: center;" | ✓</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Charged_particle_simulation&diff=899Charged particle simulation2018-01-23T14:12:40Z<p>Michael Fleming: </p>
<hr />
<div>FISPACT-II can perform simulations using neutrons and other incident charged particles. The majority of the process is exactly identical to those of simulations using neutron-induced reactions, with minor keyword and input data changes. Access to the most recent TENDL nuclear data offers the ability to simulate with incident proton, deuteron, alpha and gamma particles. To use these the only requirements are:<br />
<br />
* Add the [[Keyword:PROJECTILE | '''PROJECTILE''']] keyword with the correct modifier within the control section of the input<br />
* Modify the group structure using [[Keyword:GETXS | '''GETXS''' 1 162]], to the [[CCFE-162 group structure]]<br />
* Point the <tt>files</tt> file directories for <tt>xs_endf</tt> to the correct TENDL folder<br />
<br />
For example, the input file should begin with<br />
<br />
PROJ 3<br />
GETXS 1 162<br />
FISPACT<br />
* COLLAPSE TENDL-2017 tal-p<br />
<br />
for a proton-induced simulation. Within the <tt>files</tt> file there should be <br />
<br />
# Proton-induced cross section data<br />
xs_endf /path/to/nuclear_data/TENDL2017data/tal2015-p/gxs-162<br />
<br />
# Proton-induced fission yields<br />
fy_endf /path/to/nuclear_data/UKFY41data/ukfy4_1p<br />
<br />
Each of the possible incident particles has a different '''PROJECTILE''' number, from ('''nb: FISPACT-II version 4.0+ possesses the options 6 and 7 - previous versions do not have these options'''):<br />
<br />
# '''PROJECTILE''' 1 : Neutron ([[CCFE-709 group structure | 709]], [[UKAEA-1102 group structure | 1102]], 586 group structures)<br />
# '''PROJECTILE''' 2 : Deuteron (162 group structure)<br />
# '''PROJECTILE''' 3 : Proton (162 group structure)<br />
# '''PROJECTILE''' 4 : Alpha (162 group structure)<br />
# '''PROJECTILE''' 5 : Gamma (162 group structure)<br />
# '''PROJECTILE''' 6 : Triton (162 group structure)<br />
# '''PROJECTILE''' 7 : Helion (162 group structure)</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Docker_images&diff=898Docker images2018-01-22T14:00:52Z<p>Michael Fleming: </p>
<hr />
<div>From version 4.0 (2018), FISPACT-II is automatically built and tested using [https://www.docker.com/what-docker Docker containers]. This allows the code to be rigorously tested on multiple (over 100) operating systems/versions and with different compilers - all within a continuous integration framework and without manual intervention.<br />
<br />
FISPACT-II has been built and tested on all of the images available on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub], with regression tests performed using those tagged with <tt>_data</tt>. The suite of [[Supplied QA inputs/outputs | system test inputs/outputs]] have been drawn from these automated regression tests and users can verify results from their own system against reference results from the suite.<br />
<br />
{| class="wikitable sortable" <br />
|+ Docker images used in FISPACT-II testing<br />
! System<br />
! Version<br />
! Compiler<br />
! colspan="2" | Docker<br />
! colspan="2" | Build<br />
! colspan="2" | Github<br />
! Data<br />
|-<br />
| Ubuntu<br />
| 16.04<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:16.04_gfortran_5]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/image/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| rowspan="4" | https://img.shields.io/docker/pulls/fispact/ubuntu.svg<br />
| rowspan="4" | [https://hub.docker.com/r/fispact/ubuntu/builds/ https://img.shields.io/docker/build/fispact/ubuntu.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/16.04_gfortran_5 fispact/docker_ubuntu:16.04_gfortran_5]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/commit/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Ubuntu<br />
| 16.04<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:16.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/16.04_gfortran_7 fispact/docker_ubuntu:16.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Ubuntu<br />
| 18.04<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:18.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:18.04_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/18.04_gfortran_7 fispact/docker_ubuntu:18.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:18.04_gfortran_7.svg]<br />
|<br />
|-<br />
| Ubuntu<br />
| 17.10<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:17.10_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:17.10_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/17.10_gfortran_7 fispact/docker_ubuntu:17.10_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:17.10_gfortran_7.svg]<br />
|<br />
|-<br />
| openSUSE<br />
| 42.3<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/opensuse/ fispact/opensuse:42.3_gfortran_5]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/image/fispact/opensuse:42.3_gfortran_5.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/opensuse.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/opensuse/builds/ https://img.shields.io/docker/build/fispact/opensuse.svg]<br />
| [https://github.com/fispact/docker_opensuse/tree/42.3_gfortran_5 fispact/docker_opensuse:42.3_gfortran_5]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/commit/fispact/opensuse:42.3_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| openSUSE<br />
| 42.3<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/opensuse/ fispact/opensuse:42.3_gfortran_7]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/image/fispact/opensuse:42.3_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_opensuse/tree/42.3_gfortran_7 fispact/docker_opensuse:42.3_gfortran_7]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/commit/fispact/opensuse:42.3_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| CentOS<br />
| 7.4<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/centos/ fispact/centos:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/image/fispact/centos:7.4_gfortran_6.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/centos.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/centos/builds/ https://img.shields.io/docker/build/fispact/centos.svg]<br />
| [https://github.com/fispact/docker_centos/tree/7.4_gfortran_6 fispact/docker_centos:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/commit/fispact/centos:7.4_gfortran_6.svg]<br />
|<br />
|-<br />
| CentOS<br />
| 6.9<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/centos/ fispact/centos:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/image/fispact/centos:6.9_gfortran_6.svg]<br />
| [https://github.com/fispact/docker_centos/tree/6.9_gfortran_6 fispact/docker_centos:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/commit/fispact/centos:6.9_gfortran_6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Fedora<br />
| 27<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/fedora/ fispact/fedora:27_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/image/fispact/fedora:27_gfortran_7.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/fedora.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/fedora/builds/ https://img.shields.io/docker/build/fispact/fedora.svg]<br />
| [https://github.com/fispact/docker_fedora/tree/27_gfortran_7 fispact/docker_fedora:27_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/commit/fispact/fedora:27_gfortran_7.svg]<br />
|<br />
|-<br />
| Fedora<br />
| 26<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/fedora/ fispact/fedora:26_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/image/fispact/fedora:26_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_fedora/tree/26_gfortran_7 fispact/docker_fedora:26_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/commit/fispact/fedora:26_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| LinuxMint<br />
| 18<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/linuxmint/ fispact/linuxmint:18_gfortran_5]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/image/fispact/linuxmint:18_gfortran_5.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/linuxmint.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/linuxmint/builds/ https://img.shields.io/docker/build/fispact/linuxmint.svg]<br />
| [https://github.com/fispact/docker_linuxmint/tree/18_gfortran_5 fispact/docker_linuxmint:18_gfortran_5]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/commit/fispact/linuxmint:18_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Debian<br />
| 9<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/debian/ fispact/debian:9_gfortran_7]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/image/fispact/debian:9_gfortran_7.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/debian.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/debian/builds/ https://img.shields.io/docker/build/fispact/debian.svg]<br />
| [https://github.com/fispact/docker_debian/tree/9_gfortran_7 fispact/docker_debian:9_gfortran_7]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/commit/fispact/debian:9_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Alpine<br />
| 3.6<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/alpine/ fispact/alpine:3.6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/image/fispact/alpine:3.6_gfortran_6.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/alpine.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/alpine/builds/ https://img.shields.io/docker/build/fispact/alpine.svg]<br />
| [https://github.com/fispact/docker_alpine/tree/3.6_gfortran_6 fispact/docker_alpine:3.6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/commit/fispact/alpine:3.6_gfortran_6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| ArchLinux<br />
| latest<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/archlinux/ fispact/archlinux:latest]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/image/fispact/archlinux:latest.svg]<br />
| rowspan="1" | https://img.shields.io/docker/pulls/fispact/archlinux.svg<br />
| rowspan="1" | [https://hub.docker.com/r/fispact/archlinux/builds/ https://img.shields.io/docker/build/fispact/archlinux.svg]<br />
| [https://github.com/fispact/docker_archlinux/tree/latest_gfortran_7 fispact/docker_archlinux:latest_gfortran_7]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/commit/fispact/archlinux:latest.svg]<br />
|<br />
|-<br />
| ScientificLinux<br />
| 6<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/scientificlinux/ fispact/scientificlinux:6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6 https://images.microbadger.com/badges/image/fispact/scientificlinux:6.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/scientificlinux.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/scientificlinux/builds/ https://img.shields.io/docker/build/fispact/scientificlinux.svg]<br />
| [https://github.com/fispact/docker_scientificlinux/tree/6_gfortran_6 fispact/docker_scientificlinux:6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6 https://images.microbadger.com/badges/commit/fispact/scientificlinux:6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| ScientificLinux<br />
| 7<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/scientificlinux/ fispact/scientificlinux:7]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7 https://images.microbadger.com/badges/image/fispact/scientificlinux:7.svg]<br />
| [https://github.com/fispact/docker_scientificlinux/tree/7_gfortran_6 fispact/docker_scientificlinux:7_gfortran_6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7 https://images.microbadger.com/badges/commit/fispact/scientificlinux:7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| OracleLinux<br />
| 7.4<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/oraclelinux/ fispact/oraclelinux:7.4]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4 https://images.microbadger.com/badges/image/fispact/oraclelinux:7.4.svg]<br />
| rowspan="2" | https://img.shields.io/docker/pulls/fispact/oraclelinux.svg<br />
| rowspan="2" | [https://hub.docker.com/r/fispact/oraclelinux/builds/ https://img.shields.io/docker/build/fispact/oraclelinux.svg]<br />
| [https://github.com/fispact/docker_oraclelinux/tree/7.4_gfortran_6 fispact/docker_oraclelinux:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4 https://images.microbadger.com/badges/commit/fispact/oraclelinux:7.4.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| OracleLinux<br />
| 6.9<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/oraclelinux/ fispact/oraclelinux:6.9]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/image/fispact/oraclelinux:6.9.svg]<br />
| [https://github.com/fispact/docker_oraclelinux/tree/6.9_gfortran_6 fispact/docker_oraclelinux:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/commit/fispact/oraclelinux:6.9.svg]<br />
| style="text-align: center;" | ✓</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Docker_images&diff=897Docker images2018-01-22T12:26:52Z<p>Michael Fleming: </p>
<hr />
<div>From version 4.0 (2018), FISPACT-II is automatically built and tested using [https://www.docker.com/what-docker Docker containers]. This allows the code to be rigorously tested on multiple (over 100) operating systems/versions and with different compilers - all within a continuous integration framework and without manual intervention.<br />
<br />
FISPACT-II has been built and tested on all of the images available on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub], with regression tests performed using those tagged with <tt>_data</tt>. The suite of [[Supplied QA inputs/outputs | system test inputs/outputs]] have been drawn from these automated regression tests and users can verify results from their own system against reference results from the suite.<br />
<br />
{| class="wikitable sortable" <br />
|+ Docker images used in FISPACT-II testing<br />
! System<br />
! Version<br />
! Compiler<br />
! colspan="3" | Docker<br />
! colspan="2" | Github<br />
! Data<br />
|-<br />
| Ubuntu<br />
| 16.04<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:16.04_gfortran_5]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/image/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/version/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/16.04_gfortran_5 fispact/docker_ubuntu:16.04_gfortran_5]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_5 https://images.microbadger.com/badges/commit/fispact/ubuntu:16.04_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Ubuntu<br />
| 16.04<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:16.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/version/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/16.04_gfortran_7 fispact/docker_ubuntu:16.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:16.04_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:16.04_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Ubuntu<br />
| 18.04<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:18.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:18.04_gfortran_7.svg]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/version/fispact/ubuntu:18.04_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/18.04_gfortran_7 fispact/docker_ubuntu:18.04_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:18.04_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:18.04_gfortran_7.svg]<br />
|<br />
|-<br />
| Ubuntu<br />
| 17.10<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/ubuntu/ fispact/ubuntu:17.10_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/image/fispact/ubuntu:17.10_gfortran_7.svg]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/version/fispact/ubuntu:17.10_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_ubuntu/tree/17.10_gfortran_7 fispact/docker_ubuntu:17.10_gfortran_7]<br />
| [https://microbadger.com/images/fispact/ubuntu:17.10_gfortran_7 https://images.microbadger.com/badges/commit/fispact/ubuntu:17.10_gfortran_7.svg]<br />
|<br />
|-<br />
| openSUSE<br />
| 42.3<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/opensuse/ fispact/opensuse:42.3_gfortran_5]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/image/fispact/opensuse:42.3_gfortran_5.svg]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/version/fispact/opensuse:42.3_gfortran_5.svg]<br />
| [https://github.com/fispact/docker_opensuse/tree/42.3_gfortran_5 fispact/docker_opensuse:42.3_gfortran_5]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_5 https://images.microbadger.com/badges/commit/fispact/opensuse:42.3_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| openSUSE<br />
| 42.3<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/opensuse/ fispact/opensuse:42.3_gfortran_7]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/image/fispact/opensuse:42.3_gfortran_7.svg]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/version/fispact/opensuse:42.3_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_opensuse/tree/42.3_gfortran_7 fispact/docker_opensuse:42.3_gfortran_7]<br />
| [https://microbadger.com/images/fispact/opensuse:42.3_gfortran_7 https://images.microbadger.com/badges/commit/fispact/opensuse:42.3_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| CentOS<br />
| 7.4<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/centos/ fispact/centos:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/image/fispact/centos:7.4_gfortran_6.svg]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/version/fispact/centos:7.4_gfortran_6.svg]<br />
| [https://github.com/fispact/docker_centos/tree/7.4_gfortran_6 fispact/docker_centos:7.4_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:7.4_gfortran_6 https://images.microbadger.com/badges/commit/fispact/centos:7.4_gfortran_6.svg]<br />
|<br />
|-<br />
| CentOS<br />
| 6.9<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/centos/ fispact/centos:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/image/fispact/centos:6.9_gfortran_6.svg]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/version/fispact/centos:6.9_gfortran_6.svg]<br />
| [https://github.com/fispact/docker_centos/tree/6.9_gfortran_6 fispact/docker_centos:6.9_gfortran_6]<br />
| [https://microbadger.com/images/fispact/centos:6.9_gfortran_6 https://images.microbadger.com/badges/commit/fispact/centos:6.9_gfortran_6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Fedora<br />
| 27<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/fedora/ fispact/fedora:27_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/image/fispact/fedora:27_gfortran_7.svg]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/version/fispact/fedora:27_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_fedora/tree/27_gfortran_7 fispact/docker_fedora:27_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:27_gfortran_7 https://images.microbadger.com/badges/commit/fispact/fedora:27_gfortran_7.svg]<br />
|<br />
|-<br />
| Fedora<br />
| 26<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/fedora/ fispact/fedora:26_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/image/fispact/fedora:26_gfortran_7.svg]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/version/fispact/fedora:26_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_fedora/tree/26_gfortran_7 fispact/docker_fedora:26_gfortran_7]<br />
| [https://microbadger.com/images/fispact/fedora:26_gfortran_7 https://images.microbadger.com/badges/commit/fispact/fedora:26_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| LinuxMint<br />
| 18<br />
| gfortran-5<br />
| [https://hub.docker.com/r/fispact/linuxmint/ fispact/linuxmint:18_gfortran_5]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/image/fispact/linuxmint:18_gfortran_5.svg]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/version/fispact/linuxmint:18_gfortran_5.svg]<br />
| [https://github.com/fispact/docker_linuxmint/tree/18_gfortran_5 fispact/docker_linuxmint:18_gfortran_5]<br />
| [https://microbadger.com/images/fispact/linuxmint:18_gfortran_5 https://images.microbadger.com/badges/commit/fispact/linuxmint:18_gfortran_5.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Debian<br />
| 9<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/debian/ fispact/debian:9_gfortran_7]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/image/fispact/debian:9_gfortran_7.svg]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/version/fispact/debian:9_gfortran_7.svg]<br />
| [https://github.com/fispact/docker_debian/tree/9_gfortran_7 fispact/docker_debian:9_gfortran_7]<br />
| [https://microbadger.com/images/fispact/debian:9_gfortran_7 https://images.microbadger.com/badges/commit/fispact/debian:9_gfortran_7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| Alpine<br />
| 3.6<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/alpine/ fispact/alpine:3.6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/image/fispact/alpine:3.6_gfortran_6.svg]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/version/fispact/alpine:3.6_gfortran_6.svg]<br />
| [https://github.com/fispact/docker_alpine/tree/3.6_gfortran_6 fispact/docker_alpine:3.6_gfortran_6]<br />
| [https://microbadger.com/images/fispact/alpine:3.6_gfortran_6 https://images.microbadger.com/badges/commit/fispact/alpine:3.6_gfortran_6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| ArchLinux<br />
| latest<br />
| gfortran-7<br />
| [https://hub.docker.com/r/fispact/archlinux/ fispact/archlinux:latest]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/image/fispact/archlinux:latest.svg]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/version/fispact/archlinux:latest.svg]<br />
| [https://github.com/fispact/docker_archlinux/tree/latest fispact/docker_archlinux:latest]<br />
| [https://microbadger.com/images/fispact/archlinux:latest https://images.microbadger.com/badges/commit/fispact/archlinux:latest.svg]<br />
|<br />
|-<br />
| ScientificLinux<br />
| 6<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/scientificlinux/ fispact/scientificlinux:6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6 https://images.microbadger.com/badges/image/fispact/scientificlinux:6.svg]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6 https://images.microbadger.com/badges/version/fispact/scientificlinux:6.svg]<br />
| [https://github.com/fispact/docker_scientificlinux/tree/6 fispact/docker_scientificlinux:6]<br />
| [https://microbadger.com/images/fispact/scientificlinux:6 https://images.microbadger.com/badges/commit/fispact/scientificlinux:6.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| ScientificLinux<br />
| 7<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/scientificlinux/ fispact/scientificlinux:7]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7 https://images.microbadger.com/badges/image/fispact/scientificlinux:7.svg]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7 https://images.microbadger.com/badges/version/fispact/scientificlinux:7.svg]<br />
| [https://github.com/fispact/docker_scientificlinux/tree/7 fispact/docker_scientificlinux:7]<br />
| [https://microbadger.com/images/fispact/scientificlinux:7 https://images.microbadger.com/badges/commit/fispact/scientificlinux:7.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| OracleLinux<br />
| 7.4<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/oraclelinux/ fispact/oraclelinux:7.4]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4 https://images.microbadger.com/badges/image/fispact/oraclelinux:7.4.svg]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4 https://images.microbadger.com/badges/version/fispact/oraclelinux:7.4.svg]<br />
| [https://github.com/fispact/docker_oraclelinux/tree/7.4 fispact/docker_oraclelinux:7.4]<br />
| [https://microbadger.com/images/fispact/oraclelinux:7.4 https://images.microbadger.com/badges/commit/fispact/oraclelinux:7.4.svg]<br />
| style="text-align: center;" | ✓ <br />
|-<br />
| OracleLinux<br />
| 6.9<br />
| gfortran-6<br />
| [https://hub.docker.com/r/fispact/oraclelinux/ fispact/oraclelinux:6.9]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/image/fispact/oraclelinux:6.9.svg]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/version/fispact/oraclelinux:6.9.svg]<br />
| [https://github.com/fispact/docker_oraclelinux/tree/6.9 fispact/docker_oraclelinux:6.9]<br />
| [https://microbadger.com/images/fispact/oraclelinux:6.9 https://images.microbadger.com/badges/commit/fispact/oraclelinux:6.9.svg]<br />
| style="text-align: center;" | ✓</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Docker_images&diff=896Docker images2018-01-21T16:49:06Z<p>Michael Fleming: Created page with "From version 4.0 (2018), FISPACT-II is automatically built and tested using [https://www.docker.com/what-docker Docker containers]. This allows the code to be rigorously teste..."</p>
<hr />
<div>From version 4.0 (2018), FISPACT-II is automatically built and tested using [https://www.docker.com/what-docker Docker containers]. This allows the code to be rigorously tested on multiple (over 100) operating systems/versions and with different compilers - all within a continuous integration framework and without manual intervention.<br />
<br />
FISPACT-II has been built and tested on all of the images available on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub], with regression tests performed using those tagged with <tt>_data</tt>. The suite of [[Supplied QA inputs/outputs | system test inputs/outputs]] have been drawn from these automated regression tests and users can verify results from their own system against reference results from the suite.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=895Main Page2018-01-21T16:37:56Z<p>Michael Fleming: /* Resources for users */</p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform, set up in 2016, serves as an online resource for code users which draws heavily from the [http://fispact.ukaea.uk/wp-content/uploads/2016/06/UKAEA-R1111.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [http://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2017, ENDF/B.VIII, JENDL-4.0 and JEFF-3.3 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
*[[Docker images]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub]<br />
* [https://github.com/fispact/ FISPACT-II GitHub]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:aquamarine;width:10%;" | 4.0<br />
| style="width:10%;" | Jan 2018<br />
| This release includes code extensions to handle high-energy (MF=10) nuclear data forms including the HEIR and HEAD libraries, the addition of non-neutron covariances for uncertainty propagation, addition of triton- and helion-induced simulation, new JSON output formats and various bug-fixes. The code now has regression testing, with automated builds tested on more than 100 operating system versions. The base Docker images used for tests can be found on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker hub]. Reference outputs for these systems can be found on the system_tests folder. All new nuclear data libraries, including TENDL-2017, JEFF-3.3 and ENDF/B-VIII were processed and tested with this new version. A new python package [https://github.com/fispact/pypact pypact] for output parsing was also released. <br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=894Main Page2018-01-21T15:56:46Z<p>Michael Fleming: /* Overview */</p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform, set up in 2016, serves as an online resource for code users which draws heavily from the [http://fispact.ukaea.uk/wp-content/uploads/2016/06/UKAEA-R1111.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [http://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2017, ENDF/B.VIII, JENDL-4.0 and JEFF-3.3 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub]<br />
* [https://github.com/fispact/ FISPACT-II GitHub]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:aquamarine;width:10%;" | 4.0<br />
| style="width:10%;" | Jan 2018<br />
| This release includes code extensions to handle high-energy (MF=10) nuclear data forms including the HEIR and HEAD libraries, the addition of non-neutron covariances for uncertainty propagation, addition of triton- and helion-induced simulation, new JSON output formats and various bug-fixes. The code now has regression testing, with automated builds tested on more than 100 operating system versions. The base Docker images used for tests can be found on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker hub]. Reference outputs for these systems can be found on the system_tests folder. All new nuclear data libraries, including TENDL-2017, JEFF-3.3 and ENDF/B-VIII were processed and tested with this new version. A new python package [https://github.com/fispact/pypact pypact] for output parsing was also released. <br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=893Main Page2018-01-21T15:55:57Z<p>Michael Fleming: /* External FISPACT-II related links */</p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform, set up in 2016, serves as an online resource for code users which draws heavily from the [http://fispact.ukaea.uk/wp-content/uploads/2016/06/UKAEA-R1111.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [http://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2014, ENDF/B.VII.1, JENDL-4.0 and JEFF-3.2 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [https://hub.docker.com/u/fispact/ FISPACT-II Docker Hub]<br />
* [https://github.com/fispact/ FISPACT-II GitHub]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:aquamarine;width:10%;" | 4.0<br />
| style="width:10%;" | Jan 2018<br />
| This release includes code extensions to handle high-energy (MF=10) nuclear data forms including the HEIR and HEAD libraries, the addition of non-neutron covariances for uncertainty propagation, addition of triton- and helion-induced simulation, new JSON output formats and various bug-fixes. The code now has regression testing, with automated builds tested on more than 100 operating system versions. The base Docker images used for tests can be found on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker hub]. Reference outputs for these systems can be found on the system_tests folder. All new nuclear data libraries, including TENDL-2017, JEFF-3.3 and ENDF/B-VIII were processed and tested with this new version. A new python package [https://github.com/fispact/pypact pypact] for output parsing was also released. <br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Getting_started:_using_different_nuclear_data&diff=892Getting started: using different nuclear data2018-01-21T11:47:20Z<p>Michael Fleming: </p>
<hr />
<div><tt>FISPACT-II</tt> is distributed with numerous processed nuclear data libraries. While these libraries may be effectively interchangeable (indeed many files are actually copies from one library) for some specific simulations, such as reactor criticality, they are generally quite different. Particularly with activation calculations, many reaction channels included in some files are omitted in those from other libraries. The completeness of the TENDL data ensures that this issue does not occur, but for others erroneous simulations can occur without warnings regarding the missing data. The FNS 5-minute irradiation of Inconel-600 simulated in the [[Getting started: first example | first getting started example]] can be easily done with different nuclear data using <tt>FISPACT-II</tt>. To do this, only the <tt>files</tt> file must be modified so that it points instead to the different nuclear data. For this exercise find the <tt>getting_started/Compare_libraries/</tt> folder. This should have five folders and one script:<br />
<br />
ENDFB-7.1/ JEFF-3.2/ JENDL-4.0/ TENDL-14/<br />
plot/ fisprun<br />
<br />
Within the <tt>plot/</tt> folder, the <tt>compare.plt</tt> file contains a gnuplot script which can be run after all of the simulations are performed and <tt>FNS_2000_5min_Inconel.dat</tt> holds the experimental results from the FNS decay heat measurements from the 5 minute irradiation of an Inconel-600 sample. Each of the other folders contain all of the files required to perform the simulation with different nuclear data libraries. Before running the <tt>fisprun</tt> script, compare the files file within the <tt>ENDFB-7.1/</tt> and <tt>TENDL-14/</tt> folders. A simple <tt>diff</tt> check will return:<br />
<br />
Compare_libraries/ > diff TENDL-14/files ENDFB-7.1/files<br />
2c2<br />
< ind_nuc ../../../ENDFdata/TENDL2014data/tendl14_decay12_index<br />
---<br />
> ind_nuc ../../../ENDFdata/ENDFB71data/endfb71_index<br />
5c5<br />
< xs_endf ../../../ENDFdata/TENDL2014data/tal2014-n/gxs-709<br />
---<br />
> xs_endf ../../../ENDFdata/ENDFB71data/endfb71-n/gxs-709<br />
<br />
The only differences are in the <tt>ind_nuc</tt> (the index of nuclides) and <tt>xs_endf</tt> (the ENDF6 format cross section data) pointers, which have been altered to run over a different set of nuclides and draw particle-induced reaction data from a different folder. Similar modifications will be made in other parts of the <tt>files</tt> file in other examples. Now either run all of the inputs in each folder or run <tt>fisprun</tt> to obtain the simulation results. You should find outputs such as:<br />
<br />
Running FNS-5min Inconel-600 with TENDL-2014<br />
collapse: cpu time = 39.9 secs. 2 errors/warnings, for details see runlog<br />
condense: cpu time = 0.983 secs. 1 error/warning, for details see runlog<br />
print_lib:cpu time = 0.430 secs. No errors/warnings<br />
inventory:cpu time = 1.30 secs. 5 errors/warnings, for details see runlog<br />
Running FNS-5min Inconel-600 with ENDF/B-VII.1<br />
collapse: cpu time = 4.24 secs. 11 errors/warnings, for details see runlog<br />
condense: cpu time = 0.941 secs. 20 errors/warnings, for details see runlog<br />
print_lib:cpu time = 0.758E-01 secs. No errors/warnings<br />
inventory:cpu time = 0.702 secs. 4 errors/warnings, for details see runlog<br />
Running FNS-5min Inconel-600 with JENDL-4.0<br />
collapse: cpu time = 5.02 secs. 7 errors/warnings, for details see runlog<br />
condense: cpu time = 0.947 secs. 1 error/warning, for details see runlog<br />
print_lib:cpu time = 0.775E-01 secs. No errors/warnings<br />
inventory:cpu time = 0.719 secs. No errors/warnings<br />
Running FNS-5min Inconel-600 with JEFF3.2<br />
collapse: cpu time = 4.77 secs. 9 errors/warnings, for details see runlog<br />
condense: cpu time = 0.944 secs. 1 error/warning, for details see runlog<br />
print_lib:cpu time = 0.866E-01 secs. No errors/warnings<br />
inventory:cpu time = 0.718 secs. 3 errors/warnings, for details see runlog<br />
<br />
Note that while the condense takes approximately the same time in each run, the collapse for TENDL takes about 10× the cpu time. This is due to the much larger nuclide index, as well as the full covariance data which is processed and collapsed by <tt>FISPACT-II</tt>. Each of the folders should now contain various .out files including <tt>inventory.out</tt>, as well as the graph data file <tt>inventory.gra</tt>. The data can be easily visualised using the provided plot script:<br />
<br />
gnuplot compare.plt<br />
<br />
which should generate an encapsulated postscript file <tt>compare.eps</tt>. This should match with the figure below, which shows the decay heat curves with all simulations, the experimental results and all dominant nuclides at (x,y) positions which are their half-lives and end-of-irradiation heat contributions. In this simulation all libraries agree (within the TENDL uncertainty) on the reaction rates which produce 52V and 56Mn, but all libraries except TENDL miss the isomer production reactions and underestimate heat production around 300-3000 s. The original experimental data can be found in Maekawa et al and the validation report for <tt>FISPACT-II</tt> [http://fispact.ukaea.uk/wp-content/uploads/2016/06/CCFE-R1525.pdf fusion decay heat simulations].<br />
<br />
[[File:CompareLibs.png|550px|thumb|center| Comparison of the total heat simulations on FNS Inconel-600 produced using different nuclear data libraries distributed with FISPACT-II. ]]</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=File:CompareLibs.png&diff=891File:CompareLibs.png2018-01-21T11:42:50Z<p>Michael Fleming: </p>
<hr />
<div></div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=FISPACT-II_keywords&diff=890FISPACT-II keywords2018-01-21T11:00:02Z<p>Michael Fleming: Updated for version 4.0</p>
<hr />
<div>A run of FISPACT-II is controlled by a sequence of commands given in a user-supplied input file, the anatomy of which is described in the [[Code execution overview | code execution page]]. This requires a series of keywords to be specified for control, initial and inventory stages. Below are all of the keywords available in the most recent release of FISPACT-II, sorted by their phase and with a short description. Pages for each of the keywords are linked from this table which provide details of how to use each. Please note that as the code develops new keywords are added to allow access to new features while retaining backwards compatibility. For clarity, keywords added or modified since the 3-00-00 distribution are identified with the scheme below.<br />
<br />
{|class="wikitable"<br />
| style="background:Aquamarine;"|<br />
| Release 4.0+<br />
| style="background:#a0e75a;"|<br />
| Release 3-20-00+<br />
| style="background:Khaki;"|<br />
| Release 3-00-00+<br />
|}<br />
<br />
{| class="wikitable sortable" <br />
|+ FISPACT-II Keywords<br />
! Keyword<br />
! Version<br />
! Control<br />
! Initial<br />
! Invent.<br />
! Description<br />
|-<br />
| [[Keyword:ALLDISPEN | ALLDISPEN]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Sets the displacement energies (in eV) for all nuclides<br />
|-<br />
| [[Keyword:ATDISPEN | ATDISPEN]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Sets the displacement energies (in eV) for specified elements<br />
|-<br />
| [[Keyword:ATOMS | ATOMS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Sets initial conditions and initiates output with inventories and observables. After the [[Keyword:ZERO | ZERO]] keyword will also output uncertainties<br />
|-<br />
| [[Keyword:ATWO | ATWO]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes output of legal limits for activity in transport of radioactive material<br />
|-<br />
| [[Keyword:BREMSSTRAHLUNG | BREMSSTRAHLUNG]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes output of brehmsstrahlung contributions for specified nuclides<br />
|-<br />
| [[Keyword:CLEAR | CLEAR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes clearance data of radionuclides to be output<br />
|-<br />
| [[Keyword:CLOBBER | CLOBBER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows FISPACT-II to overwrite existing output with same name<br />
|-<br />
| [[Keyword:CNVTYPE | CNVTYPE]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the user to specify formalism for conversion of incident particle spectra<br />
|-<br />
| [[Keyword:COVARIANCE | COVARIANCE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes cross-channel covariances to be calculated (if present in nuclear data)<br />
|-<br />
| [[Keyword:CULTAB | CULTAB]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Produces additional lines in tab files for specific post-processing tools<br />
|-<br />
| [[Keyword:CUMFYLD | CUMFYLD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the cumulative fission yields to be read, rather than the default independent yields<br />
<br />
|-<br />
| [[Keyword:DENSITY | DENSITY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specifies a density of the material in grams per cubic centimetre<br />
|-<br />
| [[Keyword:DEPLETION | DEPLETION]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes FISPACT-II to output the uncertainty from all depletion processes for a set of specified nuclides<br />
|-<br />
| [[Keyword:DOSE | DOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows modification of the dose rate values from semi-infinite slab to point sources<br />
|-<br />
| [[Keyword:END | END]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Terminates the input of the simulation<br />
|-<br />
| [[Keyword:ENDPULSE | ENDPULSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Terminates the [[Keyword:PULSE | PULSE]] phase in the simulation<br />
|-<br />
| [[Keyword:ERROR | ERROR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows manual override of error values for uncertainty quantification<br />
|-<br />
| [[Keyword:FISCHOOSE | FISCHOOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to select actinides for pathways-based uncertainty - note that this does not affect the use of fission in the inventory simulation<br />
|-<br />
| [[Keyword:FISPACT | FISPACT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| A divider keyword which separates the library data preparation, initialising that process before subsequent actions<br />
|-<br />
| [[Keyword:FISYIELD | FISYIELD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to specify which fission yields are read and included in the inventory simulation<br />
|-<br />
| [[Keyword:FLUX | FLUX]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Used to specify an incident particle flux in particles per square centimetre per second<br />
|-<br />
| [[Keyword:FUEL | FUEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specification of initial inventory by nuclide, rather than by element (which is done using [[Keyword:MASS | MASS]])<br />
|-<br />
| [[Keyword:FULLXS | FULLXS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the full, energy-dependent group cross sections to be stored when the library is being collapsed<br />
|-<br />
| [[Keyword:GENERIC | GENERIC]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Produces generic pathways data removing isomeric transitions<br />
|-<br />
| [[Keyword:GETDECAY | GETDECAY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the condense of decay data or reading of a pre-compiled binary file<br />
|-<br />
| [[Keyword:GETXS | GETXS]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Initiates the collapse of an incident particle spectrum with the cross sections to generate one-group values. Now with the ability to use arbirtary (ebins) incident group structure<br />
|-<br />
| [[Keyword:GRAPH | GRAPH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the output of summarised graph files and plotting scripts in a variety of possible formats<br />
|-<br />
| [[Keyword:GROUP | GROUP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the specification of an output gamma group structure<br />
|-<br />
| [[Keyword:GRPCONVERT | GRPCONVERT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the conversion of an incident spectrum from one multi group to another<br />
|-<br />
| [[Keyword:HALF | HALF]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes half-lives of all nuclides to be output at each step<br />
|-<br />
| [[Keyword:HAZARDS | HAZARDS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Reads in ingestion/inhalation doses and outputs contributions from all nuclides at all steps<br />
|-<br />
| [[Keyword:INDEXPATH | INDEXPATH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes index of nuclides significant pathways to be written out<br />
|-<br />
| [[Keyword:IRON | IRON]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Special keyword for low-impurity iron simulation, to remove iron responses and allow high-accuracy impurity analyses<br />
|-<br />
| [[Keyword:LIBVERSION | LIBVERSION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Controls input data format, allowing legacy EAF data to be used<br />
|-<br />
| [[Keyword:LIMGRP | LIMGRP]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Clips the incident particle spectrum at minimum and/or maximum energies, summing into the lowest and/or highest groups<br />
|-<br />
| [[Keyword:LOGLEVEL | LOGLEVEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Controls the sophistication of the logging outputs, particularly useful for error identification<br />
|-<br />
| [[Keyword:LOOKAHEAD | LOOKAHEAD]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Fine-tunes pathway analyses by searching for long-lived nuclides and including them in post-irradiation dominant lists<br />
|-<br />
| [[Keyword:MASS | MASS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Input inventory specification by element, instead of by nuclide (as done with the [[Keyword:FUEL | FUEL]] keyword)<br />
|-<br />
| [[Keyword:MCSAMPLE | MCSAMPLE]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Used in conjunction with [[Keyword:SENSITIVITY | SENSITIVITY]] to change the Monte-Carlo sampling of nuclear data uncertainties. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:MCSEED | MCSEED]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows specification of random number seeds in Monte-Carlo sensitivity calculations<br />
|-<br />
| [[Keyword:MIND | MIND]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Sets a minimum number of nuclides to follow in the simualation<br />
|-<br />
| [[Keyword:MONITOR | MONITOR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Controls whether or not FISPACT-II will output a description of the execution steps to the terminal<br />
|-<br />
| [[Keyword:NOCOMP | NOCOMP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the elemental composition table to be omitted from the output<br />
|-<br />
| [[Keyword:NOERROR | NOERROR]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Turns off uncertainty from nuclear data files, although manual inclusion of error can be done using [[Keyword:ERROR | ERROR]]<br />
|-<br />
| [[Keyword:NOFISS | NOFISS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Stops the use of fission yield data from being processed and then used in the simulation<br />
|-<br />
| [[Keyword:NOSORT | NOSORT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Removes the output of dominant nuclides and subsequent pathways/uncertainty data<br />
|-<br />
| [[Keyword:NOSTABLE | NOSTABLE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Removes stable nuclides from the output files<br />
|-<br />
| [[Keyword:NOT1 | NOT1]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB1 | TAB1]]<br />
|-<br />
| [[Keyword:NOT2 | NOT2]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB2 | TAB2]]<br />
|-<br />
| [[Keyword:NOT3 | NOT3]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB3 | TAB3]]<br />
|-<br />
| [[Keyword:NOT4 | NOT4]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Switches off the output of [[Keyword:TAB4 | TAB4]]<br />
|-<br />
| [[Keyword:NUCGRAPH | NUCGRAPH]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| <br />
| style="text-align: center;" | ✓<br />
| <br />
| Creates data outputs and plot scripts with break-downs for all individual dominant nuclides (as opposed to integral quantities)<br />
|-<br />
| [[Keyword:OVER | OVER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the manual overriding of cross sections, half-lives and their errors<br />
|-<br />
| [[Keyword:PARTITION | PARTITION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Allows the partitioning of the inventory by element, making multiple parallel simulations<br />
|-<br />
| [[Keyword:PATH | PATH]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Specifies a specific pathway which will be included in the pathways analysis<br />
|-<br />
| [[Keyword:PATHRESET | PATHRESET]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Initiates a new pathways search and uncertainty quantification at the post-irradiation step that it is called in<br />
|-<br />
| [[Keyword:POWER | POWER]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Causes the incident particle flux to be renormalised to match a specified volumetric power, using full kerma values from the nuclear data<br />
|-<br />
| [[Keyword:PRINTLIB | PRINTLIB]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the printing of a range of library data, check the keyword options for more guidance<br />
|-<br />
| [[Keyword:PROBTABLE | PROBTABLE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Specifies the method of application of self-shielding factors<br />
|-<br />
| [[Keyword:PROJECTILE | PROJECTILE]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Selects the incident particle used in the simulations, for example neutron or one of the four other charged particles currently allowed. As of version 4.0, two additional options have been added for triton- and helion- induced reaction data<br />
|-<br />
| [[Keyword:PULSE | PULSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Initiates a set of repeated irradiation steps with given flux and duration, must be ended with [[Keyword:ENDPULSE | ENDPULSE]]<br />
|-<br />
| [[Keyword:READGG | READGG]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Allows the user to specify an output gamma group structure for decay sources<br />
|-<br />
| [[Keyword:READSF | READSF]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the reading and use of spontaneous fission yield data<br />
|-<br />
| [[Keyword:RESULT | RESULT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Outputs the total number of atoms tracked in pathways analyses for the specified nuclides<br />
|-<br />
| [[Keyword:ROUTES | ROUTES]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| A method for specifying a range of pathways between two nuclides for inclusion in the pathways analyses<br />
|-<br />
| [[Keyword:SAVELINES | SAVELINES]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes spectral lines from the decay data to be stored and can be further printed using the [[Keyword:PRINTLIB | PRINTLIB 5]] option<br />
|-<br />
| [[Keyword:SENSITIVITY | SENSITIVITY]]<br />
| style="white-space:nowrap;background:Khaki;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes sensitivity calculations to be performed over a specified set of nuclides and reactions. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:SORTDOMINANT | SORTDOMINANT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Controls the number of nuclides to blue included in the dominant lists and used in uncertainty quantification<br />
|-<br />
| [[Keyword:SPECTRUM | SPECTRUM]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Alternative to [[Keyword:ATOMS | ATOMS]] which suppresses the full inventory output and gives the gamma spectrum<br />
|-<br />
| [[Keyword:SPEK | SPEK]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes calculation of an approximate gamma spectrum for nuclides which have no spectral data<br />
|-<br />
| [[Keyword:SPLIT | SPLIT]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the display of additional gamma and beta heat data in the final summary table<br />
|-<br />
| [[Keyword:SSFCHOOSE | SSFCHOOSE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Selects the set of nuclides for which self-shielding factors will be applied<br />
|-<br />
| [[Keyword:SSFDILUTION | SSFDILUTION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows manual override of dilution values for self-shielding factor calculation in a group-by-group basis<br />
|-<br />
| [[Keyword:SSFFUEL | SSFFUEL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the specification of inventory to be used in the calculation of dilutions and self-shielding factors by nuclide (instead of by element, as with [[Keyword:SSFMASS | SSFMASS]])<br />
|-<br />
| [[Keyword:SSFGEOMETRY | SSFGEOMETRY]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Provides spatial self-shielding using the universal sigmoid curve for foils, wires, spheres and cylinders<br />
|-<br />
| [[Keyword:SSFMASS | SSFMASS]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the specification of inventory to be used in the calculation of dilutions and self-shielding factors by element (instead of by nuclide, as with [[Keyword:SSFFUEL | SSFFUEL]])<br />
|-<br />
| [[Keyword:STEP | STEP]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Performs the same function of [[Keyword:ATOMS | ATOMS]] but suppresses the output data <br />
|-<br />
| [[Keyword:TAB1 | TAB1]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the inventory data (atoms and mass) to a two column TAB1 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB2 | TAB2]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the activity and dose rate from each nuclide to a two column TAB2 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB3 | TAB3]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes the ingestion and inhalation dose from each nuclide to a two column TAB3 file for easy post-processing<br />
|-<br />
| [[Keyword:TAB4 | TAB4]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Writes a multi-group gamma spectrum to a TAB4 file<br />
|-<br />
| [[Keyword:TIME | TIME]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Sets the time-steps in the simulation and triggers the processing of any keyword actions that have been queued<br />
|-<br />
| [[Keyword:TOLERANCE | TOLERANCE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the modification of solver tolerance values<br />
|-<br />
| [[Keyword:UNCERTAINTY | UNCERTAINTY]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes the code to perform pathways-based uncertainty quantification and allows manual control of algorithm parameters. As of version 4.0, this will take non-neutron uncertainty data from full covariance files<br />
|-<br />
| [[Keyword:UNCTYPE | UNCTYPE]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Allows the user to specify the uncertainties used in the simulation, including cross sections and/or half-lives<br />
|-<br />
| [[Keyword:USEFISSION | USEFISSION]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| <br />
| Causes fission yields to be included in the inventory matrix<br />
|-<br />
| [[Keyword:USESPALLATION | USESPALLATION]]<br />
| style="white-space:nowrap;background:aquamarine;" | 4.0<br />
| style="text-align: center;" | ✓ <br />
| <br />
| <br />
| Causes the <tt>sp_endf</tt> and <tt>xs_endf</tt> files for specified nuclides to be spliced at a user-supplied energy and recorded in the <tt>xs_extra</tt> directory before being used in subsequent simulation<br />
|-<br />
| [[Keyword:WALL | WALL]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| style="text-align: center;" | ✓ <br />
| style="text-align: center;" | ✓ <br />
| Allows the input of a neutron first wall loading in surface power, which will renormalise the incident particle flux<br />
|-<br />
| [[Keyword:XSTHRESHOLD | XSTHRESHOLD]]<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-20-00<br />
| style="text-align: center;" | ✓ <br />
| <br />
|<br />
| Controls the treshold minimum cross section for inclusion required for inclusion in the calculation<br />
|-<br />
| [[Keyword:ZERO | ZERO]]<br />
| style="white-space:nowrap;background:Khaki;" | 3-00-00<br />
| <br />
| <br />
| style="text-align: center;" | ✓ <br />
| Resets the time and moves the simulation into the cooling phase, initiates pathways analyses, uncertainty calculations and output of [[Keyword:GRAPH | GRAPH]] data</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=889Main Page2018-01-21T10:47:57Z<p>Michael Fleming: /* Release History */</p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform, set up in 2016, serves as an online resource for code users which draws heavily from the [http://fispact.ukaea.uk/wp-content/uploads/2016/06/UKAEA-R1111.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [http://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2014, ENDF/B.VII.1, JENDL-4.0 and JEFF-3.2 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:aquamarine;width:10%;" | 4.0<br />
| style="width:10%;" | Jan 2018<br />
| This release includes code extensions to handle high-energy (MF=10) nuclear data forms including the HEIR and HEAD libraries, the addition of non-neutron covariances for uncertainty propagation, addition of triton- and helion-induced simulation, new JSON output formats and various bug-fixes. The code now has regression testing, with automated builds tested on more than 100 operating system versions. The base Docker images used for tests can be found on the [https://hub.docker.com/u/fispact/ FISPACT-II Docker hub]. Reference outputs for these systems can be found on the system_tests folder. All new nuclear data libraries, including TENDL-2017, JEFF-3.3 and ENDF/B-VIII were processed and tested with this new version. A new python package [https://github.com/fispact/pypact pypact] for output parsing was also released. <br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Charged_particle_simulation&diff=888Charged particle simulation2017-10-20T07:59:08Z<p>Michael Fleming: </p>
<hr />
<div>FISPACT-II can perform simulations using neutrons and other incident charged particles. The majority of the process is exactly identical to those of simulations using neutron-induced reactions, with minor keyword and input data changes. Access to the most recent TENDL nuclear data offers the ability to simulate with incident proton, deuteron, alpha and gamma particles. To use these the only requirements are:<br />
<br />
* Add the [[Keyword:PROJECTILE | '''PROJECTILE''']] keyword with the correct modifier within the control section of the input<br />
* Modify the group structure using [[Keyword:GETXS | '''GETXS''' 1 162]], to the [[CCFE-162 group structure]]<br />
* Point the <tt>files</tt> file directories for <tt>xs_endf</tt> to the correct TENDL folder<br />
<br />
For example, the input file should begin with<br />
<br />
PROJ 3<br />
GETXS 1 162<br />
FISPACT<br />
* COLLAPSE TENDL-2015 tal-p<br />
<br />
for a proton-induced simulation. Within the <tt>files</tt> file there should be <br />
<br />
# Proton-induced cross section data<br />
xs_endf /path/to/fispact/ENDFdata/TENDL2015data/tal2015-p/gxs-162<br />
<br />
# Proton-induced fission yields<br />
fy_endf /path/to/fispact/ENDFdata/TENDL2015data/tal2015-p/ukfy4_1p<br />
<br />
Each of the possible incident particles has a different '''PROJECTILE''' number, from:<br />
<br />
# '''PROJECTILE''' 1 : Neutron ([[CCFE-709 group structure | 709]], [[UKAEA-1102 group structure | 1102]], 586 group structures)<br />
# '''PROJECTILE''' 2 : Deuteron (162 group structure)<br />
# '''PROJECTILE''' 3 : Proton (162 group structure)<br />
# '''PROJECTILE''' 4 : Alpha (162 group structure)<br />
# '''PROJECTILE''' 5 : Gamma (162 group structure)</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Spectra_conversion&diff=887Spectra conversion2017-10-20T07:58:12Z<p>Michael Fleming: </p>
<hr />
<div>The nuclear data provided in the FISPACT-II releases includes multi-group cross sections which are processed in complex procedures for use in the code. While it is possible to have multi-group data in other group structures (contact the UKAEA nuclear data manager if required), the provided nuclear data are multi-purpose and more than cover nearly any application. To simulate with a user-supplied particle spectrum, the energy discretisation must be identical, so a non-compliant particle spectrum must be converted into a suitable group structure. <br />
<br />
This is a common issue for simulations performed using codes with coarse energy treatment or legacy results which are only available in some (typically low-density) alternative group structure. Users are '''strongly advised''' to calculate particle spectra in a compatible group if possible, however the built-in group conversion tools may be used if no alternative is available.<br />
<br />
Legacy EAF data was provided in several multi-group formats including micro-flux weightings which varied depending on the group and application. Besides the benefits of using ENDF-format data and the TENDL data in particular, the use of coarse groups and application-specific group weightings is a serious handicap for many simulations. <br />
<br />
<br />
= Example flux convert =<br />
<br />
To modify a flux spectrum, FISPACT-II has a [[Keyword:GRPCONVERT | '''GRPCONVERT''']] keyword which can be used to re-bin an artibrary flux spectrum. The flux_convert/ folder within getting started has an example using a spectrum from a hafnium foil irradiation at FNG. For this conversion only these three files are required: <tt>arb_flux</tt> provides a list of energy boundaries for the original group structure, <tt>convert.i</tt> contains the simple input<br />
<br />
<< convert flux to 709 group structure>><br />
GRPCONVERT 175 709<br />
FISPACT<br />
* SPECTRAL MODIFICATION<br />
END<br />
* END<br />
<br />
and the <tt>files</tt> file only must contain <tt>ind_nuc</tt>, a pointer to the <tt>arb_flux</tt> and an output <tt>fluxes</tt> file - for example:<br />
<br />
<pre><br />
# Nuclide index file<br />
/path/to/fispact/ENDFdata/decay/decay_2012_index_2012<br />
<br />
# arb_flux location<br />
arb_flux /path/to/my/arb_flux<br />
<br />
# ouptut fluxes file<br />
fluxes /path/to/my/output/fluxes<br />
</pre><br />
<br />
This fluxes file can then be used in simulations which collapse with the provided TENDL libraries, for example. '''Please note''' that the 175 group structure contains one group from 1.0E-5 to 1.0E-1 eV. Converting this massive bin will result in an extrapolated, flat spectrum to 1.0E-5 eV in the 709 group which will be collapsed with a 1/v cross section and yield unphysical results. In general, groups with such coarse structure cannot be reasonably used to model multiple regions where the specific flux weighting used to process the data will not be valid - and a flat weighted coarse structure will result in useless simulations. The user must at minimum clip the groups to physically realistic values or, if accurate results are desired (particularly if the reaction rate is non-negligible in the energy range in question), calculate the spectrum in a group structure which captures the physics of the system.<br />
<br />
The getting_started example can be executed with<br />
<br />
fispact convert files.convert<br />
<br />
where the specific <tt>files</tt> file has been specified. FISPACT-II will generate a detailed output which summarises the input spectrum, distribution of flux by groups in the new structure, and the converted particle spectrum. There will also be a new spectrum file, <tt>fluxes</tt>, which is in the correct format for subsequent simulations. The equal-lethargy spectra before and after conversion for the example case is shown below. Note that this should be nearly identical to the original spectrum, with some differences where resonance-related discontinuities are present in the original spectrum.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=886Main Page2017-07-13T16:04:50Z<p>Michael Fleming: /* Release History */</p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform, set up in 2016, serves as an online resource for code users which draws heavily from the [http://fispact.ukaea.uk/wp-content/uploads/2016/06/UKAEA-R1111.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [http://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2014, ENDF/B.VII.1, JENDL-4.0 and JEFF-3.2 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Former supported release<br />
| style="background:Aquamarine;"|<br />
| Current supported release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:Aquamarine;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=ENDF_file_definitions_and_supplied_nuclear_data&diff=885ENDF file definitions and supplied nuclear data2017-07-13T16:03:39Z<p>Michael Fleming: /* Decay radiation types */</p>
<hr />
<div>FISPACT-II employs the standard ENDF reaction <tt>mt</tt> and other numbers to identify incident particle reactions, residual nuclide production, dpa, kerma, decay processes, fission yields, etc, depending on the library used and the completeness of the data. Below are descriptive lists which serve as a dictionary between the ENDF-6 values, corresponding FISPACT-II internal values, physical description and the details of the code use of these data. For more information on the the ENDF-6 format, see the [https://www.bnl.gov/isd/documents/70393.pdf ENDF-6 Manual].<br />
<br />
==Neutron-induced reaction <tt>mt</tt> numbers==<br />
<br />
The table below lists all of the possible incident-particle reaction <tt>mt</tt> numbers that are read by FISPACT-II, as well as their products, N-Z modification of the parent, number of and species of the secondary particles. Note that two values <tt>mt</tt>=5,18 result in the removal of the parent nuclide and residuals are handled by a separate set of rules that employ <tt>mf</tt>=10 residual yields or <tt>mf</tt>=8 fission yields. For <tt>mf</tt>=10, the residual product data must be available in the incident-particle files and for <tt>mf</tt>=8 the user must employ the [[Keyword:USEFISSION | '''USEFISSION''']] keyword and specify the requested fission yields. For more information see the [[Getting started: fission decay heat pulse | fission example simulation]].<br />
<br />
{| class="wikitable sortable" <br />
|+ Neutron induced reactions recognised by FISPACT-II<br />
! Projectile<br />
! Products<br />
! MT<br />
! dZ<br />
! dZ<br />
! NSEC<br />
! Secondaries<br />
|-<br />
| n<br />
| total <br />
| 1 <br />
| 0 <br />
| 0 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| E <br />
| 2 <br />
| 0 <br />
| 0 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| nonel <br />
| 3 <br />
| 0 <br />
| 0 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| n <br />
| 4 <br />
| 0 <br />
| 0 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| O <br />
| 5 <br />
| <br />
| <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| 2nd <br />
| 11 <br />
| -1 <br />
| -3 <br />
| 1 <br />
| \(^{2}\)H <br />
|-<br />
| n<br />
| 2n <br />
| 16 <br />
| 0 <br />
| -1 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| 3n <br />
| 17 <br />
| 0 <br />
| -2 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| F <br />
| 18 <br />
| <br />
| <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| nα <br />
| 22 <br />
| -2 <br />
| -4 <br />
| 1 <br />
| \(^{4}\)He <br />
|-<br />
| n<br />
| n3α <br />
| 23 <br />
| -6 <br />
| -12 <br />
| 3 <br />
| \(^{4}\)He \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| 2nα <br />
| 24 <br />
| -2 <br />
| -5 <br />
| 1 <br />
| \(^{4}\)He <br />
|-<br />
| n<br />
| 3nα <br />
| 25 <br />
| -2 <br />
| -6 <br />
| 1 <br />
| \(^{4}\)He <br />
|-<br />
| n<br />
| np <br />
| 28 <br />
| -1 <br />
| -1 <br />
| 1 <br />
| \(^{1}\)H <br />
|-<br />
| n<br />
| n2α <br />
| 29 <br />
| -4 <br />
| -8 <br />
| 2 <br />
| \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| 2n2α <br />
| 30 <br />
| -4 <br />
| -9 <br />
| 2 <br />
| \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| nd <br />
| 32 <br />
| -1 <br />
| -2 <br />
| 1 <br />
| \(^{2}\)H <br />
|-<br />
| n<br />
| nt <br />
| 33 <br />
| -1 <br />
| -3 <br />
| 1 <br />
| \(^{3}\)H <br />
|-<br />
| n<br />
| nh <br />
| 34 <br />
| -2 <br />
| -3 <br />
| 1 <br />
| \(^{3}\)He <br />
|-<br />
| n<br />
| nd2α <br />
| 35 <br />
| -5 <br />
| -10 <br />
| 3 <br />
| \(^{2}\)H \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| nt2α <br />
| 36 <br />
| -5 <br />
| -11 <br />
| 3 <br />
| \(^{3}\)H \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| 4n <br />
| 37 <br />
| 0 <br />
| -3 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| 2np <br />
| 41 <br />
| -1 <br />
| -2 <br />
| 1 <br />
| \(^{1}\)H <br />
|-<br />
| n<br />
| 3np <br />
| 42 <br />
| -1 <br />
| -3 <br />
| 1 <br />
| \(^{1}\)H <br />
|-<br />
| n<br />
| n2p <br />
| 44 <br />
| -2 <br />
| -2 <br />
| 2 <br />
| \(^{1}\)H \(^{1}\)H <br />
|-<br />
| n<br />
| npα <br />
| 45 <br />
| -3 <br />
| -5 <br />
| 2 <br />
| \(^{1}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| γ <br />
| 102 <br />
| 0 <br />
| 1 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| p <br />
| 103 <br />
| -1 <br />
| 0 <br />
| 1 <br />
| \(^{1}\)H <br />
|-<br />
| n<br />
| d <br />
| 104 <br />
| -1 <br />
| -1 <br />
| 1 <br />
| \(^{2}\)H <br />
|-<br />
| n<br />
| t <br />
| 105 <br />
| -1 <br />
| -2 <br />
| 1 <br />
| \(^{3}\)H <br />
|-<br />
| n<br />
| h <br />
| 106 <br />
| -2 <br />
| -2 <br />
| 1 <br />
| \(^{3}\)He <br />
|-<br />
| n<br />
| α <br />
| 107 <br />
| -2 <br />
| -3 <br />
| 1 <br />
| \(^{4}\)He <br />
|-<br />
| n<br />
| 2α <br />
| 108 <br />
| -4 <br />
| -7 <br />
| 2 <br />
| \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| 3α <br />
| 109 <br />
| -6 <br />
| -11 <br />
| 3 <br />
| \(^{4}\)He \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| 2p <br />
| 111 <br />
| -2 <br />
| -1 <br />
| 2 <br />
| \(^{1}\)H \(^{1}\)H <br />
|-<br />
| n<br />
| pα <br />
| 112 <br />
| -3 <br />
| -4 <br />
| 2 <br />
| \(^{1}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| t2α <br />
| 113 <br />
| -5 <br />
| -10 <br />
| 3 <br />
| \(^{3}\)H \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| d2α <br />
| 114 <br />
| -5 <br />
| -9 <br />
| 3 <br />
| \(^{2}\)H \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| pd <br />
| 115 <br />
| -2 <br />
| -2 <br />
| 2 <br />
| \(^{1}\)H \(^{2}\)H <br />
|-<br />
| n<br />
| pt <br />
| 116 <br />
| -2 <br />
| -3 <br />
| 2 <br />
| \(^{1}\)H \(^{3}\)H <br />
|-<br />
| n<br />
| dα <br />
| 117 <br />
| -3 <br />
| -5 <br />
| 2 <br />
| \(^{2}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| 5n <br />
| 152 <br />
| 0 <br />
| -4 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| 6n <br />
| 153 <br />
| 0 <br />
| -5 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| 2nt <br />
| 154 <br />
| -1 <br />
| -4 <br />
| 1 <br />
| \(^{3}\)H <br />
|-<br />
| n<br />
| tα <br />
| 155 <br />
| -3 <br />
| -6 <br />
| 2 <br />
| \(^{3}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| 4np <br />
| 156 <br />
| -1 <br />
| -4 <br />
| 1 <br />
| \(^{1}\)H <br />
|-<br />
| n<br />
| 3nd <br />
| 157 <br />
| -1 <br />
| -4 <br />
| 1 <br />
| \(^{2}\)H <br />
|-<br />
| n<br />
| ndα <br />
| 158 <br />
| -3 <br />
| -6 <br />
| 2 <br />
| \(^{2}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| 2npα <br />
| 159 <br />
| -3 <br />
| -6 <br />
| 2 <br />
| \(^{1}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| 7n <br />
| 160 <br />
| 0 <br />
| -6 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| 8n <br />
| 161 <br />
| 0 <br />
| -7 <br />
| 0 <br />
| <br />
|-<br />
| n<br />
| 5np <br />
| 162 <br />
| -1 <br />
| -5 <br />
| 1 <br />
| \(^{1}\)H <br />
|-<br />
| n<br />
| 6np <br />
| 163 <br />
| -1 <br />
| -6 <br />
| 1 <br />
| \(^{1}\)H <br />
|-<br />
| n<br />
| 7np <br />
| 164 <br />
| -1 <br />
| -7 <br />
| 1 <br />
| \(^{1}\)H <br />
|-<br />
| n<br />
| 4nα <br />
| 165 <br />
| -2 <br />
| -7 <br />
| 1 <br />
| \(^{4}\)He <br />
|-<br />
| n<br />
| 5nα <br />
| 166 <br />
| -2 <br />
| -8 <br />
| 1 <br />
| \(^{4}\)He <br />
|-<br />
| n<br />
| 6nα <br />
| 167 <br />
| -2 <br />
| -9 <br />
| 1 <br />
| \(^{4}\)He <br />
|-<br />
| n<br />
| 7nα <br />
| 168 <br />
| -2 <br />
| -10 <br />
| 1 <br />
| \(^{4}\)He <br />
|-<br />
| n<br />
| 4nd <br />
| 169 <br />
| -1 <br />
| -5 <br />
| 1 <br />
| \(^{2}\)H <br />
|-<br />
| n<br />
| 5nd <br />
| 170 <br />
| -1 <br />
| -6 <br />
| 1 <br />
| \(^{2}\)H <br />
|-<br />
| n<br />
| 6nd <br />
| 171 <br />
| -1 <br />
| -7 <br />
| 1 <br />
| \(^{2}\)H <br />
|-<br />
| n<br />
| 3nt <br />
| 172 <br />
| -1 <br />
| -5 <br />
| 1 <br />
| \(^{3}\)H <br />
|-<br />
| n<br />
| 4nt <br />
| 173 <br />
| -1 <br />
| -6 <br />
| 1 <br />
| \(^{3}\)H <br />
|-<br />
| n<br />
| 5nt <br />
| 174 <br />
| -1 <br />
| -7 <br />
| 1 <br />
| \(^{3}\)H <br />
|-<br />
| n<br />
| 6nt <br />
| 175 <br />
| -1 <br />
| -8 <br />
| 1 <br />
| \(^{3}\)H <br />
|-<br />
| n<br />
| 2nh <br />
| 176 <br />
| -2 <br />
| -4 <br />
| 1 <br />
| \(^{3}\)He <br />
|-<br />
| n<br />
| 3nh <br />
| 177 <br />
| -2 <br />
| -5 <br />
| 1 <br />
| \(^{3}\)He <br />
|-<br />
| n<br />
| 4nh <br />
| 178 <br />
| -2 <br />
| -6 <br />
| 1 <br />
| \(^{3}\)He <br />
|-<br />
| n<br />
| 3n2p <br />
| 179 <br />
| -2 <br />
| -4 <br />
| 2 <br />
| \(^{1}\)H \(^{1}\)H <br />
|-<br />
| n<br />
| 3n2α <br />
| 180 <br />
| -4 <br />
| -10 <br />
| 2 <br />
| \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| 3npα <br />
| 181 <br />
| -3 <br />
| -7 <br />
| 2 <br />
| \(^{1}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| dt <br />
| 182 <br />
| -2 <br />
| -4 <br />
| 2 <br />
| \(^{2}\)H \(^{3}\)H <br />
|-<br />
| n<br />
| npd <br />
| 183 <br />
| -2 <br />
| -3 <br />
| 2 <br />
| \(^{1}\)H \(^{2}\)H <br />
|-<br />
| n<br />
| npt <br />
| 184 <br />
| -2 <br />
| -4 <br />
| 2 <br />
| \(^{1}\)H \(^{3}\)H <br />
|-<br />
| n<br />
| ndt <br />
| 185 <br />
| -2 <br />
| -5 <br />
| 2 <br />
| \(^{2}\)H \(^{3}\)H <br />
|-<br />
| n<br />
| nph <br />
| 186 <br />
| -3 <br />
| -4 <br />
| 2 <br />
| \(^{1}\)H \(^{3}\)He <br />
|-<br />
| n<br />
| ndh <br />
| 187 <br />
| -3 <br />
| -5 <br />
| 2 <br />
| \(^{2}\)H \(^{3}\)He <br />
|-<br />
| n<br />
| nth <br />
| 188 <br />
| -3 <br />
| -6 <br />
| 2 <br />
| \(^{3}\)H \(^{3}\)He <br />
|-<br />
| n<br />
| ntα <br />
| 189 <br />
| -3 <br />
| -7 <br />
| 2 <br />
| \(^{3}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| 2n2p <br />
| 190 <br />
| -2 <br />
| -3 <br />
| 2 <br />
| \(^{1}\)H \(^{1}\)H <br />
|-<br />
| n<br />
| ph <br />
| 191 <br />
| -3 <br />
| -3 <br />
| 2 <br />
| \(^{1}\)H \(^{3}\)He <br />
|-<br />
| n<br />
| dh <br />
| 192 <br />
| -3 <br />
| -4 <br />
| 2 <br />
| \(^{2}\)H \(^{3}\)He <br />
|-<br />
| n<br />
| hα <br />
| 193 <br />
| -4 <br />
| -6 <br />
| 2 <br />
| \(^{3}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| 4n2p <br />
| 194 <br />
| -2 <br />
| -5 <br />
| 2 <br />
| \(^{1}\)H \(^{1}\)H <br />
|-<br />
| n<br />
| 4n2α <br />
| 195 <br />
| -4 <br />
| -11 <br />
| 2 <br />
| \(^{4}\)He \(^{4}\)He <br />
|-<br />
| n<br />
| 4npα <br />
| 196 <br />
| -3 <br />
| -8 <br />
| 2 <br />
| \(^{1}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| 3p <br />
| 197 <br />
| -3 <br />
| -2 <br />
| 3 <br />
| \(^{1}\)H \(^{1}\)H \(^{1}\)H <br />
|-<br />
| n<br />
| n3p <br />
| 198 <br />
| -3 <br />
| -3 <br />
| 3 <br />
| \(^{1}\)H \(^{1}\)H \(^{1}\)H <br />
|-<br />
| n<br />
| 3n2pα <br />
| 199 <br />
| -4 <br />
| -8 <br />
| 3 <br />
| \(^{1}\)H \(^{1}\)H \(^{4}\)He <br />
|-<br />
| n<br />
| 5n2p <br />
| 200 <br />
| -2 <br />
| -6 <br />
| 2 <br />
| \(^{1}\)H \(^{1}\)H <br />
|}<br />
<br />
==Derived induced-particle reaction <tt>mt</tt> numbers==<br />
<br />
Several nuclear data values are not provided in the raw ENDF data, requiring summation where desired (such as gas production by species) or semi-empirical formulae to generate derived quantities such as ''kerma'' or ''dpa''. These are done through the nuclear data processing scripts that are used to generate the nuclear data supplied with FISPACT-II. The following data are listed with their <tt>mt</tt> numbers and a physical description. <br />
<br />
Note that these are for user information and do not affect the nuclide inventories, hence the lack of columns from the previous table.<br />
<br />
{| class="wikitable" <br />
|+ Derived MT numbers read by FISPACT-II, including gas production, dpa and kerma<br />
! MT<br />
! Description<br />
|-<br />
| 201 <br />
| (z,Xn) Total neutron production <br />
|-<br />
| 202 <br />
| (z,X\(\gamma\)) Total gamma production<br />
|-<br />
| 203 <br />
| (z,Xp) Total proton production<br />
|-<br />
| 204 <br />
| (z,Xd) Total deuteron production<br />
|-<br />
| 205 <br />
| (z,Xt) Total triton production<br />
|-<br />
| 206 <br />
| (z,Xh) Total helion (3He) production<br />
|-<br />
| 207 <br />
| (z,Xα) Total alpha particle production<br />
|-<br />
|<br />
| <br />
|-<br />
| 301 <br />
| Kerma total (eV-barns) <br />
|-<br />
| 302 <br />
| Kerma elastic<br />
|-<br />
| 303 <br />
| Kerma non-elastic (all but mt=2)<br />
|-<br />
| 304 <br />
| Kerma inelastic (mt={51-91})<br />
|-<br />
| 318 <br />
| Kerma fission (mt=18 or mt= {19, 20, 21, 38})<br />
|-<br />
| 401 <br />
| Kerma disappearance (mt={102-120})<br />
|-<br />
| 402 <br />
| Kerma radiative capture (mt=102)<br />
|-<br />
| 403 <br />
| Kerma proton production (mt=103)<br />
|-<br />
| 407 <br />
| Kerma α production (mt=107)<br />
|-<br />
| 442 <br />
| Total photon (eV-barns)<br />
|-<br />
| 443 <br />
| Total kinematic kerma (high limit)<br />
|-<br />
| <br />
|<br />
|-<br />
| 444 <br />
| Dpa total (eV-barns)<br />
|-<br />
| 445 <br />
| Dpa elastic (mt=2)<br />
|-<br />
| 446 <br />
| Dpa inelastic (mt={51-91})<br />
|-<br />
| 447 <br />
| Dpa disappearance (mt={102-120})<br />
|}<br />
<br />
==Radioactive decay processes==<br />
<br />
FISPACT-II allows 27 decay processes and 9 decay radiation types that are used to follow the nuclide inventory and generate decay radiation source terms, respectively. These are summarised below.<br />
<br />
===Decay types===<br />
<br />
The table below gives the internal <tt>IRT</tt> numbers and their ENDF-6 correspondence, as well as the parent nuclide N-Z shift, number and species of secondaries and how the code reports the decay in output data. Note that thres values <tt>IRT</tt>=6,17,27 result in the removal of the parent nuclide and residuals are handled by a separate set of rules that employ spontaneous fission yields. The user must employ the [[Keyword:READSF | '''READSF''']] keyword and include a <tt>sf_endf</tt> directory in the <tt>files</tt> file.<br />
<br />
{| class="wikitable" <br />
|+ Decay types from <tt>MT</tt>=457 utilised by FISPACT-II<br />
! <tt>STYP</tt><br />
! <tt>RTYP</tt><br />
! Description<br />
! \(\Delta Z\)<br />
! \(\Delta A\)<br />
! Code<br />
! <tt>NSEC</tt><br />
! Secs<br />
|-<br />
| 1 <br />
| 1 <br />
| \(\beta^-\) decay <br />
| 1 <br />
| 0 <br />
| <tt>b-</tt> <br />
| 0 <br />
| <br />
|-<br />
| 2 <br />
| 2 <br />
| \(\beta^+\) decay or electron capture <br />
|\(-\)1 <br />
| 0 <br />
| <tt>b+</tt><br />
| 0 <br />
| <br />
|-<br />
| 3 <br />
| 3 <br />
| isomeric transition (IT) <br />
| 0 <br />
| 0 <br />
| <tt>IT</tt> <br />
| 0 <br />
|<br />
|-<br />
| 4 <br />
| 4 <br />
| \(\alpha\) decay <br />
| \(-\)2 <br />
| \(-\)4 <br />
| <tt>a</tt> <br />
| 1 <br />
| \(^4\)He<br />
|-<br />
| 5 <br />
| 5 <br />
| neutron emission <br />
| 0 <br />
| \(-\)1 <br />
| <tt>n</tt> <br />
| 0 <br />
|<br />
|-<br />
| 6 <br />
| 6 <br />
| spontaneous fission (SF) <br />
| \(-\)999 <br />
| \(-\)999 <br />
| <tt>SF</tt> <br />
| 0 <br />
|<br />
|-<br />
| 7 <br />
| 7 <br />
| proton emission <br />
| \(-\)1 <br />
| \(-\)1 <br />
| <tt>p</tt> <br />
| 1 <br />
| \(^1\)H<br />
|-<br />
| 8 <br />
| 8 <br />
| not used <br />
| 0 <br />
| 0 <br />
| 0 <br />
| <br />
| <br />
|-<br />
| 9 <br />
| 9 <br />
| not used <br />
| 0 <br />
| 0 <br />
| 0 <br />
| <br />
| <br />
|-<br />
| 10 <br />
| 10 <br />
| unknown <br />
| 0 <br />
| 0 <br />
| 0 <br />
| <br />
| <br />
|-<br />
| 11 <br />
| 1.5 <br />
| \(\beta^-\) decay + neutron emission <br />
| 1 <br />
| \(-\)1 <br />
| <tt>b-n</tt> <br />
| 0 <br />
|<br />
|-<br />
| 12 <br />
| 1.4 <br />
| \(\beta^-\) decay + \(\alpha\) emission <br />
| \(-\)1 <br />
| \(-\)4 <br />
| <tt>b-a</tt> <br />
| 1 <br />
| \(^4\)He<br />
|-<br />
| 13 <br />
| 2.4 <br />
| \(\beta^+\) decay + \(\alpha\) emission <br />
| \(-\)3 <br />
| \(-\)4 <br />
| <tt>b+a</tt> <br />
| 1 <br />
| \(^4\)He<br />
|-<br />
| 14 <br />
| 2.7 <br />
| \(\beta^+\) decay + proton emission <br />
| \(-\)2 <br />
| \(-\)1 <br />
| <tt>b+p</tt> <br />
| 1 <br />
| \(^1\)H<br />
|-<br />
| 15 <br />
| 3.4 <br />
| IT followed by \(\alpha\) emission <br />
| \(-\)2 <br />
| \(-\)4 <br />
| <tt>IT+a</tt> <br />
| 1 <br />
| \(^4\)He<br />
|-<br />
| 16 <br />
| 1.1 <br />
| double \(\beta^-\) decay <br />
| 2 <br />
| 0 <br />
| <tt>b-b-</tt> <br />
| 0 <br />
| <br />
|-<br />
| 17 <br />
| 1.6 <br />
| \(\beta^-\) decay followed by SF <br />
| \(-\)999 <br />
| \(-\)999 <br />
| <tt>b-SF</tt> <br />
| 0 <br />
| <br />
|-<br />
| 18 <br />
| 7.7 <br />
| double proton emission <br />
| \(-\)2 <br />
| \(-\)2 <br />
| <tt>pp</tt> <br />
| 2 <br />
| \(^1\)H \(^1\)H<br />
|-<br />
| 19 <br />
| 2.2 <br />
| double \(\beta^+\) or electron capture <br />
| \(-\)2 <br />
| 0 <br />
| <tt>b+b+</tt> <br />
| 0 <br />
| <br />
|-<br />
| 20 <br />
| 1.55 <br />
| \(\beta^-\) and double neutron emission <br />
| 1 <br />
| \(-\)2 <br />
| <tt>b-2n</tt> <br />
| 0 <br />
| <br />
|-<br />
| 21 <br />
| 1.555 <br />
| \(\beta^-\) and triple neutron emission <br />
| 1 <br />
| \(-\)3 <br />
| <tt>b-3n</tt><br />
| 0 <br />
| <br />
|-<br />
| 22 <br />
| 1.5555 <br />
| \(\beta^-\) and quadruple neutron emission <br />
| 1 <br />
| \(-\)4 <br />
| <tt>b-4n</tt> <br />
| 0 <br />
| <br />
|-<br />
| 23 <br />
| 5.5 <br />
| double neutron emission <br />
| 0 <br />
| \(-\)2 <br />
| <tt>2n</tt> <br />
| 0 <br />
| <br />
|-<br />
| 24 <br />
| 5.55 <br />
| triple neutron emission <br />
| 0 <br />
| \(-\)3 <br />
| <tt>3n</tt> <br />
| 0 <br />
| <br />
|-<br />
| 25 <br />
| 2.77 <br />
| \(\beta^+\) decay + double proton emission <br />
| \(-\)3 <br />
| \(-\)2 <br />
| <tt>b+2p</tt> <br />
| 2 <br />
| \(^1\)H \(^1\)H<br />
|-<br />
| 26 <br />
| 2.777 <br />
| \(\beta^+\) decay + triple proton emission <br />
| \(-\)4 <br />
| \(-\)3 <br />
| <tt>b+3p</tt> <br />
| 3 <br />
| \(^1\)H \(^1\)H \(^1\)H<br />
|-<br />
| 27 <br />
| 2.6 <br />
| \(\beta^+\) decay followed by SF <br />
| \(-\)999 <br />
| \(-\)999 <br />
| <tt>b+SF</tt> <br />
| 0 <br />
| <br />
|}<br />
<br />
===Decay radiation types===<br />
<br />
For decay radiation, FISPACT-II allows 9 radiation types which are taken from the ENDF-6 manual. Their physical description and how the code reports the data are summarised in the table below.<br />
<br />
{| class="wikitable" <br />
|+ Decay radiation types from <tt>MT</tt>=457 utilised by FISPACT-II<br />
! <tt>STYP</tt><br />
! colspan="2" | Radiation type<br />
! Code<br />
|-<br />
| 0 <br />
| \(\gamma\)<br />
| gamma rays<br />
| <tt>gamma</tt><br />
|-<br />
| 1 <br />
| \(\beta^-\)<br />
| beta rays<br />
| <tt>beta</tt><br />
|-<br />
| 2 <br />
| ec,\(\beta^+\)<br />
| electron capture and/or positron emission<br />
| <tt>ec, beta+</tt><br />
|-<br />
| 3<br />
| <br />
| not known<br />
| <tt>not known</tt><br />
|-<br />
| 4<br />
| \(\alpha\)<br />
| alpha particles<br />
| <tt>alpha</tt><br />
|-<br />
| 5<br />
| \(n\)<br />
| neutrons<br />
| <tt>n</tt><br />
|-<br />
| 6<br />
| SF<br />
| spontaneous fission fragments<br />
| <tt>SF</tt><br />
|-<br />
| 7<br />
| \(p\)<br />
| protons<br />
| <tt>p</tt><br />
|-<br />
| 8<br />
| \(e^-\)<br />
| "discrete electrons"<br />
| <tt>e-</tt><br />
|-<br />
| 9 <br />
| \(x\)<br />
| X-rays and annihilation radiation<br />
| <tt>x</tt><br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Reaction_extract&diff=884Reaction extract2017-07-13T15:58:43Z<p>Michael Fleming: </p>
<hr />
<div>The natural function of the FISPACT-II collapse is to reduce the full multi-group cross section data and a user-supplied incident particle spectrum into one-group effective cross sections to obtain reaction rates. For many reasons it may be desirable to have the full energy-dependent reaction rates and energy-dependent uncertainties available for visualisation and/or checking purposes.<br />
<br />
A seprate utility programme, <tt>extract_xs_endf</tt> allows the user to specify specific reactions and extract a variety of data on the energy-dependant reaction rates. It takes in the following arguments:<br />
<br />
# <tt>fileroot</tt> name for the output, which will generate <tt>fileroot.out</tt> and <tt>fileroot.log</tt><br />
# projectile, given as a letter from the choices of: n, p, d, a, g<br />
# energy group of the nuclear data, taken from the possible [[UKAEA-1102 group structure | 1102]], [[CCFE-709 group structure | 709]] or [[CCFE-162 group structure | 162]] group structures<br />
# parent nuclide, which is the target nuclide for the reaction<br />
# the <tt>mt</tt> number of the reaction, which must be drawn from the allowable values in the [[ENDF file definitions and supplied nuclear data | FISPACT-II <tt>mt</tt> list]]<br />
# daughter nuclide, which is the product of the specific reaction - note that isomers are defined in the usual way, e.g. In116m<br />
# [optional] the name of the <tt>files</tt> file (default <tt>files</tt>)<br />
<br />
The <tt>files</tt> file must include a nuclide index file <tt>ind_nuc</tt>, incident particle spectrum <tt>fluxes</tt> file and the directory for the cross section data <tt>xs_endf</tt>, for example:<br />
<br />
# Index of nuclides to be included<br />
ind_nuc /path/to/fispact/ENDFdata/TENDL2015data/tendl15_decay12_index<br />
# Incident particle spectrum<br />
fluxes /some/data/directory/my_fluxes<br />
# Library cross section data<br />
xs_endf /path/to/fispact/ENDFdata/TENDL2015data/tal2015-n/gxs-709<br />
<br />
An example execution would be:<br />
<br />
extract_xs_endf U238_capture n 709 U238 102 U239<br />
<br />
which would generate <tt>U238_capture.out</tt> with an eight column output including:<br />
<br />
# En-low = lower energy of the group<br />
# En-high = higher energy of the group<br />
# flux = group flux(i), as in the flux file<br />
# flux-unc = 0.000000E+00 (this feature is turned off in distributed versions)<br />
# gxs = group cross section, as in the TENDL file<br />
# gxs_unc = mapped variance one sigma of the group cross section, in %<br />
# greac-rate= flux(i)*gxs(i)/flux(1:709)<br />
# cum-rate = incremental sum of the greaction-rates, in %</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Main_Page&diff=881Main Page2017-06-29T13:47:12Z<p>Michael Fleming: </p>
<hr />
<div>[[File:Fispact-ii.jpg|frame|right|alt=FISPACT-II]]<br />
<br />
Welcome to the FISPACT-II Wiki. This platform, set up in 2016, serves as an online resource for code users which draws heavily from the [http://fispact.ukaea.uk/wp-content/uploads/2016/06/UKAEA-R1111.pdf User Manual] and provides a comprehensive description of the code, keywords and physics, as well as [[Getting_started_examples | tutorial examples]]. If you are interested in editing this wiki, please request an account through the [http://fispact.ukaea.uk/contact FISPACT-II website contact page] or [http://fispact.ukaea.uk/forum FISPACT-II forum].<br />
<br />
<br />
<br />
<strong>Please note that this wiki is limited to the content of the current released versions of FISPACT-II and not intended as a forum for discussion of development, bugs, code feedback, questions, etc -- for all of these there exists a [https://fispact.ukaea.uk/forum FISPACT-II forum]. For more general information, please visit the [http://fispact.ukaea.uk FISPACT-II homepage].</strong><br />
<br />
== Overview ==<br />
<br />
FISPACT-II is an enhanced multiphysics inventory and nuclear observables system providing a wide variety of advanced simulation methods and employing the most up-to-date and complete nuclear data for both neutron and charged-particle interactions.<br />
<br />
<br />
FISPACT-II has been developed and is maintained by the United Kingdom Atomic Energy Authority at Culham. As a comprehensive, modern object-oriented Fortran code, FISPACT-II fully processes all ENDF-6 nuclear data including the complete TENDL data with full covariances files. This extends the physics up to GeV energy with all channels and incident/emitted particles. Code features include self-shielding factors, broad temperature dependence, thin/thick target yields, robust pathway analysis, Monte-Carlo sensitivity and uncertainty quantification and propagation using full covariance data.<br />
<br />
<br />
The latest generation of processing codes PREPRO, NJOY and CALENDF are used to provide the user with the most sophisticated incident-particle nuclear data from the TENDL-2014, ENDF/B.VII.1, JENDL-4.0 and JEFF-3.2 international libraries, which is complemented with the latest decay and fission yield data, including the most recent GEF libraries. The maturity of modern, technological nuclear data including TENDL and GEF provides truly comprehensive data for all simulation requirements. The result is a multiphysics platform that can accommodate the needs of all nuclear applications including: activation, transmutation, depletion, burn-up, decays, source definition, full inventories, dpa, kerma, primary damage (PKA) spectra, gas/radionuclide production and more.<br />
<br />
== Quick links within FISPACT-II Wiki ==<br />
<br />
{{col-begin}}<br />
{{Col-3}}<br />
=== Getting started ===<br />
<br />
*[[Installing FISPACT-II]]<br />
*[[Code execution overview]]<br />
*[[Getting started examples]]<br />
*[[Charged particle simulation]]<br />
*[[Spectra conversion]]<br />
<br />
=== Utility programs ===<br />
<br />
*[[Spectra-PKA]]<br />
*[[Nuclear data I/O optimisation]]<br />
*[[Reaction extract]]<br />
<br />
{{Col-3}}<br />
<br />
=== Useful reference information ===<br />
<br />
*[[FISPACT-II keywords]]<br />
*[[Nuclear data forms]]<br />
*[[Output interpretation]]<br />
*[[Supplied QA inputs/outputs]]<br />
*[[ENDF file definitions and supplied nuclear data]]<br />
<br />
=== Advanced feature descriptions ===<br />
*[[Kerma-based POWER renormalisation]]<br />
*[[Probability table self-shielding]]<br />
*[[Monte-Carlo sensitivity]]<br />
*[[Pathways-based uncertainty]]<br />
*[[Thin/thick target yields]]<br />
<br />
{{Col-3}}<br />
<br />
=== Resources for users ===<br />
<br />
*[[Reference input spectra]]<br />
*[[User licences]]<br />
*[[Verification and validation]]<br />
*[[Materials handbooks]]<br />
{{col-end}}<br />
<br />
== External FISPACT-II related links ==<br />
<br />
* [http://fispact.ukaea.uk FISPACT-II homepage]<br />
* [https://fispact.ukaea.uk/forum FISPACT-II forum]<br />
* [http://www.ccfe.ac.uk/fispact.aspx CCFE FISPACT-II homepage]<br />
* [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA Data Bank FISPACT-II page]<br />
* [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC FISPACT-II page]<br />
* [https://www.gov.uk/government/organisations/uk-atomic-energy-authority UK Atomic Energy Authority homepage]<br />
<br />
== Release History ==<br />
<br />
The code history is not comprehensive before release 3-00-00, but contains summaries of the major releases and details of the additions in the recent code versions. Since the code development is essentially linear and backwards compatibility is carefully maintained, users are encouraged to update to the most recent code distribution available. <br />
<br />
{|class="wikitable"<br />
| style="background:Salmon;"|<br />
| Legacy version without support<br />
| style="background:Khaki;"|<br />
| Former release without support<br />
| style="background:#a0e75a;"|<br />
| Current supported release<br />
| style="background:Aquamarine;"|<br />
| Upcoming release<br />
|}<br />
<br />
{| class="wikitable" style="width:100%;"<br />
|+ Release history<br />
|-<br />
! Name<br />
! Version<br />
! Release Date<br />
! Highlights<br />
! Distribution<br />
|- style="vertical-align:top;"<br />
| style="width:10%;" | FISPACT-II<br />
| style="white-space:nowrap;background:Aquamarine;width:10%;" | 3-20-00<br />
| style="width:10%;" | Dec 2016<br />
| This code version includes the addition of several new, major features including enhanced energy-dependent fission yield treatment, depletion uncertainty, new graphical outputs, free gamma source discretisations, arbitrary incident particle energy groups, displacement damage energy threhsold modification, new incident-particle spectrum conversion algorithms, <tt>files</tt> file-less simulation and more. The [[FISPACT-II_keywords | keywords page]] highlights the new keywords with more detailed descriptions of their use.<br />
| style="width:10%;" | [http://fispact.ukaea.uk/contact UKAEA]<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:#a0e75a;" | 3-00-00<br />
| Oct 2015<br />
| This version marks the change to ENDF-format libraries as the default format for the nuclear data libraries, although capability to read EAF-2010 libraries is retained as an option. Fission yield processing has been updated: spontaneaous fission yields are now included, and the user can select either cumulative or instantaneous fission yield data. A POWER keyword has been introduced to allow fission power to be used to define the irradiating flux (for ENDF only). The processing of variance-covariance, uncertainty quantification and propagation has been improved. This release includes TENDL-2014, ENDFB-VII.1, JEFF-3.2 and JENDL 4.0u nuclear data libraries and the capability to read and process them. It can compress these to allow faster collapse calculations. The code can handle n, p, d, α and γ irradiation, There is a new interface module that allows inventories to computed for multiple flux spectra and returned to a calling program. There is also a separate Fispact MP program that allows inventory calculations to be performed for simulataneous irradiation by several different projectiles.<br />
| [http://fispact.ukaea.uk/contact UKAEA], [http://www.oecd-nea.org/tools/abstract/detail/nea-1890/ OECD-NEA DataBank], [https://rsicc.ornl.gov/codes/ccc/ccc8/ccc-836.html RSICC] and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 2-00-00<br />
| <br />
| The major change introduced in Release 2.0 of FISPACT-II was the addition of the reading and processing of alternative ENDF-format library data sets to meet the needs of the enhanced capabilities. This caused a major overhaul of the data input parts of the software and a huge expansion of the number of nuclides and reactions that can be treated; better fission yield data and cross-section data in more energy groups up to higher energies can now be used. This version can also handle more irradiating projectiles (γ, n, p, d, α) and provides additional diagnostic outputs (kerma, dpa and gas appm rates) if the ENDF-format library contains the required input data.<br />
<br />
Features added in Release 2.10 are self-shielding using the universal sigmoid curve approximation, processing of covariances between different reactions, extended pathways analysis features, handling additional isomeric states and the capability to use the TENDL library data.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| FISPACT-II<br />
| style="white-space:nowrap;background:Khaki;" | 1-00-00<br />
| <br />
| This version began the process of extending the activation-transmutation prediction capability whilst maintaining the validation heritage of FISPACT-2007. New pathways and new monte-carlo sensitivity capabilities were introduced to extend both pathways and sensitivity calculations to multi-pulse irradiation cases. The reading and processing of CALENDF probability table data was introduced in the calculation of cross-section collapse to include self-shielding effects in the inventory calculations.<br />
| UKAEA, UK universities, European collaborators and commercial customers<br />
|- style="vertical-align:top;"<br />
| EASY-2010<br />
| style="white-space:nowrap;background:Salmon;" | 2010, 2007 and previous<br />
| <br />
| These legacy versions of the code do not support ENDF-6 data and rely upon EAF data that is deprecated. Various other issues have been addressed in the re-development, including: use of an outdated ODE solution method, lack of rigorous uncertainty propagation and unsupportable software development process which results in numerous bugs without any foreseeable fix. Users are very strongly encouraged to make use of one of the modern releases.<br />
| The legacy code versions have been distributed over the past 20 years to over 150 different establishments in 28 countries, including a 12 commercial licenses. Deprecated code.<br />
|}</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Supplied_QA_inputs/outputs&diff=880Supplied QA inputs/outputs2017-03-10T15:00:45Z<p>Michael Fleming: </p>
<hr />
<div>Supplied with Version 3.00 of the FISPACT-II software are 185 test input files in the <tt>fispQA2010</tt> directory and 324 test input files in the <tt>fispQA</tt> directory together with test output and log files to illustrate the running of FISPACT-II for a variety of irradiation and cooling scenarios, using all the di erent EAF and ENDF library files and illustrating the use of all the [[FISPACT-II keywords]].<br />
<br />
The <tt>fispQA</tt> test set provides tests that use the now default ENDF format libraries introduced in Version 2 for cross sections, fission yields and decay, and the new CALENDF output files for the probability tables used in calculating self-shielding. It is<br />
recommended that you use these libraries rather than the older EAF format libraries as they provide you with better and more extensive nuclear data. The usage of the keywords for the two libraries is almost identical, and if you find an example using nthe EAF libraries then you can easily translate it into an example using the ENDF libraries following the procedure outlined in [[Converting legacy inputs | converting legacy inputs]].<br />
<br />
'''Note that some of the test cases issue warnings and some terminate with fatal error messages. The purpose of these test cases is to illustrate the nerrors that are issued if obsolescent keywords are used, or if keywords are used incorrectly in the input file.'''<br />
<br />
While the [[Getting started examples | getting started examples]] give several introductory simulations and the descriptions provided in the [[FISPACT-II keywords | keyword pages]] give technical descriptions for the required parameters, working examples of each keyword may be found by simple <tt>grep</tt> probing of the QA folders. For example, a search for uncertainty calculations within the <tt>fispQA2010</tt> would return:<br />
<br />
.../fispQA2010> grep UNCER Tst_*/*.i<br />
Tst_162deut/test33.i:UNCERT 3<br />
Tst_162deut/test34.i:UNCERT 3<br />
Tst_162prot/test3.i:UNCERT 3<br />
...<br />
Tst_709fis/test117.i:UNCERT 2<br />
Tst_709fis/test118.i:UNCERT 2<br />
Tst_709fns/Ag.i:UNCERT 2<br />
...<br />
<br />
Reference calculations are provided in the QA folders (''again not that some demonstrate errors and error logging'') which can be checked by hand or through tools such as <tt>diff</tt>. It is recommended that new installations be checked by automatic running of the QA suite using the provided scripts. For more description see the [[Installing FISPACT-II | installing FISPACT-II]] section.</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Keyword:CLOBBER&diff=879Keyword:CLOBBER2017-03-10T14:59:37Z<p>Michael Fleming: </p>
<hr />
<div><br />
{{big|'''CLOBBER'''}}<br />
<br />
----<br />
<br />
In order to prevent accidental loss of data, the default action of FISPACT-II is to terminate with a fatal error if output files of the same names as speci ed in the current run already exist in the present working directory. This keyword allows existing output files to be overwritten without any error messages from the program.<br />
<br />
Example usage:<br />
<br />
< -- Control phase -- ><br />
CLOBBER<br />
...<br />
FISPACT<br />
* Title of the simulation<br />
< -- Initial phase -- > <br />
...<br />
< -- Inventory phase -- > <br />
...</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Nuclear_data_forms&diff=878Nuclear data forms2017-03-10T14:59:12Z<p>Michael Fleming: /* Probability Tables */</p>
<hr />
<div>FISPACT-II requires connection to several nuclear data libraries and forms before it can be used to calculate inventories. While any libraries in the correct ENDF-6 format could be used (with suitable processing), the development of FISPACT-II over the last several years has run in parallel with the development of the TALYS-based Evaluated Nuclear Data Library TENDL project and those libraries are the recommended source of cross section data forms. Together FISPACT-II and TENDL's nuclear data forms make up the simulation platform that is a complete package tailored for all application needs: nuclear fission and fusion, nuclear fuel cycle, accelerator physics, isotope production, material characterisation, storage and life cycle, earth exploration, astrophysics, homeland security and more. <br />
<br />
=Overview=<br />
<br />
The following data libraries are required:<br />
<br />
# Cross section data for neutron, proton, deuteron, alpha and gamma-induced reactions<br />
# Fission yields data for neutron, proton, deuteron, alpha and gamma-induced reactions<br />
# Variance-covaraiance data for neutron-induced reactions<br />
# Probability tables data for neutron-induced reactions in the resonance energy ranges<br />
# Decay data<br />
# Radiological data:<br />
#* Biological hazard data<br />
#* Legal transport data<br />
#* Clearance data<br />
<br />
To streamline, simplify and control any feature of all the nuclear data assimilation processes, the code development philosophy has been to follow in all aspects as much as possible the format described in the [https://www.bnl.gov/isd/documents/70393.pdf ENDF-6 format manual]. Three processing codes are used in sequence and in parallel to produce, process, check, and compare the nuclear data forms: NJOY12-050, PREPRO-2015 and CALENDF-2010. All the processing steps cannot be handled by only one or even two of those unique processing codes, a combination of the three is needed to extract the data forms that are the most useful in all applications. A schematic of the processing sequences is shown in the figure below. <br />
<br />
=Cross Section Data=<br />
<br />
The principal sources of cross-section data are the di erent generations of the TALYS-based Evaluated Nuclear Data Libraries. The latest TENDL-2015 is the recommended evaluated data source for use in any type of nuclear technology applications. The principal advances of this new library are in the unique target coverage, over 2800 nuclides; the upper energy range, 200 MeV; variance-covariance information for all nuclides; and the extension to cover all important projectiles: neutron, proton, deuteron, alpha and gamma, and last but not least the proven capacity of this type of library to transfer regularly to technology the feedbacks of extensive validation, veri cation and benchmark activities from one release to the next. TENDL is the sixth generation of such a library and as such has bene ted from the previous releases since TENDL-2008, as well as a [http://fispact.ukaea.uk/documentation-2/ wide range of modern V&V].<br />
<br />
The cross sections are provided in a set of group structures including:<br />
<br />
*[[UKAEA-1102 group structure | UKAEA-1102]] general-purpose neutron group structure<br />
*[[CCFE-162 group structure | CCFE-162]] incident charged particle group structure<br />
*[[CCFE-709 group structure | CCFE-709]] fusion neutron group structure<br />
*CASMO-586 fission reactor group structure<br />
*Several legacy groups are available with deprecated EAF libraries<br />
<br />
While the neutron data is contained in the finer 709 and 1102 multi-groups, the 162 scheme for the non-resonant p, d, α and γ-induced cross-sections is used. The data format used is fully compliant with the ENDF-6 manual specification handled on an isotopic basis and so allows many existing utility codes further to manipulate, visualise or check any aspects of the pre-processed files. The data files are produced using a complex but robust, complementary sequence of modules of the processing codes NJOY12-050 and PREPRO-2015. During the processing outputs from veri cation and validation steps are regularly taken in order to establish the validity of all computed derived data. To be able to account for Doppler broadening effects the processed files are given at three reactor temperatures: 293.6, 600 and 900 degree Kelvin and two astrophysical temperatures: 5 and 30 keV.<br />
<br />
=Fission Yield Data=<br />
<br />
The fission yield data need to be provided for each actinide and incident particle. The files are supplied in an ENDF-6 format and are read by FISPACT-II with no further processing. A library is provided based on the JEFF-3.1.1 library for neutron-induced fission. Only 19 of the many nuclides that have ssion have any ssion yield data in JEFF-3.1.1 and these cover only a reduced energy range. For the remainder the UKFY4.2 library then further extends the range before a neighbouring fission yield is used. This UKFY4.2 library using Wahl's systematics is also used for all other particle induced fission yields.<br />
<br />
[http://www.khs-erzhausen.de/GEF.html GEF-based fission-fragment yield libraries] in ENDF-6 format are also provided: GEFY-5.2 as independent and cumulative ssion-fragment yields with multi-chance fission. The uncertainties are given and reflect the uncertainties of the model. They are determined from calculations with perturbed model parameters. 109 spontaneous and 119 neutron induced ssion, including target in isomeric state are provided on a fine 49 incident energy grid structure up to 20 MeV.<br />
<br />
=Variance and Covariance Data=<br />
<br />
Above the upper energy of the resolved resonance range, for each of the 2800+ isotopes a Monte Carlo method in which the covariance data come from uncertainties of the nuclear model calculations is used. A complete description of the procedure is given in [dx.doi.org/10.1016/j.nima.2008.02.003 this reference]. For all isotopes, the initial "best" set of results is produced by a TALYS calculation with an adjusted input parameter set. This set of results is stored in a set of sampeld ENDF files MF-3 to MF-10. For each isotope, many TALYS runs with random nuclear model parameters are performed, which are used to generate and correlations. As well as correlation within the same reaction channels, correlation between reaction channels is included. All information on cross section covariance is stored in the MF-33 format, starting at the end of the resonance range up to 200 MeV. Short-range, self-scaling variance components are also specified for each MT type.<br />
<br />
The data format used to store the variance-covariance information has been made fully compliant with the ENDF-6 format description and the files are read directly by FISPACT-II without any further processing. <br />
<br />
=Probability Tables=<br />
<br />
The CALENDF nuclear data processing system is used to convert the evaluation defining the cross-sections in ENDF-6 format (i.e., the resonance parameters, both resolved and unresolved) into forms useful for applications. Those forms used to describe neutron cross-section uctuations correspond to cross section probability tables", based on Gauss quadratures and effective cross-sections. The CALENDF-2010 code provides those probability tables in the energy range from 0.1 eV up to the end of the resolved or the unresolved resonance range. Probability table data in 709 group formats are provided for the majority of isotopes of the TENDL library. These data are used to model dilution effects from channel, isotopic or elemental interferences. To account for Doppler broadening effects the tables are given at three temperatures: 293.6, 600 and 900 degree Kelvin.<br />
<br />
=Decay Data=<br />
<br />
In addition to cross-sections the other basic quantities required by an inventory code are information on the decay properties (such as half-life) of all the nuclides considered. These data are available in a handful of evaluated decay data libraries. FISPACT-II is able to read the data directly in ENDF-6 format; it requires no pre-processing to be done. The eaf_dec_2010 library, based primarily on the JEFF-3.1.1 and JEF-2.2 radioactive decay data libraries with additional data from the latest UK evaluations UKPADD6.10, contain 2233 nuclides. However, to handle the extension in incident particle type, energy range and number of targets, many more are needed. A new 3875-nuclide decay library UKDD-12 has been assembled from eaf_dec_2010 complemented with all of JEFF-3.1.1, a handful of ENDF/B-VII.1 and other decay files to cover the range of daughters of TENDL and short lived ssion products.<br />
<br />
There remain compatibility issues between the isomer de nitions arising from the cross section library, through the RIPL-3 database and the newly assembled decay library. Historical incompatibilities in isomeric state number (g, m, n, o, . . . ) and energy levels between radionuclide daughter products of reactions and the associated decay data files will need to be addressed in a future release.<br />
<br />
=Other Nuclear Data Libraries=<br />
<br />
FISPACT-II is compatible with all fully ENDF-6 compliant nuclear data forms which have been suitably processed and provided in the required multigroup stuctures. Several libraries are distributed with the code, including the most recent neutron-incident, fission yield and decay data from ENDF/B, JENDL and JEFF. <br />
<br />
==ENDF/B Nuclear Data Libraries==<br />
<br />
The Cross Section Evaluation Working Group (CSEWG) released the ENDF/B-VII.1 library on 22 December 2011. The ENDF/B-VII.1 library is the US latest recommended evaluated nuclear data le for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0, including: many new evaluation in the neutron sublibrary (423 in all) and over 190 of these contain covariances, new ssion product yields for 31 isotopes and a greatly expanded decay data sublibrary for 3817 radionuclides.<br />
<br />
For more details, visit [http://www.nndc.bnl.gov/endf/b7.1/ the NNDC offical website].<br />
<br />
==JENDL Nuclear Data Libraries==<br />
<br />
The purpose of JENDL-4.0 is to provide a Japanese standard library for fast breeder reactors, thermal reactors, fusion neutronics and shielding calculations, and other applications. The data libraries used have been updated to the JENDL-4.0u level of August 2013 for both the neutron reaction and ssion yields sublibrary. JENDL FP Decay Data File 2011 contains decay data of 1284 FP nuclides (of which 142 nuclides are stable) that includes recent TAGS (Total Absorption Gamma-ray Spectroscopy) information.<br />
<br />
For more details, visit [http://wwwndc.jaea.go.jp/jendl/j40/j40.html the JAEA official website].<br />
<br />
==JEFF Nuclear Data Libraries==<br />
<br />
The Joint Evaluated Fission and Fusion File is an evaluated library produced via an international collaboration of Data Bank member countries co-ordinated by the JEFF Scientific Co-ordination Group, under the auspices of the NEA Data Bank. The new JEFF-3.2 general purpose library has been released on March 5, 2014 in ENDF-6 format and contains incident neutron data for 472 nuclides or elements from 1-H-1 to 100-Fm-255.<br />
<br />
For more details, visit [https://www.oecd-nea.org/dbforms/data/eva/evatapes/jeff_32/ the OECD-NEA official website].<br />
<br />
==CENDL Nuclear Data Libraries==<br />
<br />
The CENDL-3.1 neutron-induced cross section data was not released in the most recent FISPACT-II 3.00 version, but is available in the 709 group structure ENDF-6 format files directly from [http://www.ccfe.ac.uk/easy-data/FISPACT-II/ENDFdata/CENDL31data.tgz the FISPACT-II online nuclear data repository]. The compressed file is approximately 26 Mb in size. It is recommended that users install the uncompressed files within their FISPACT-II installation directory under ENDFdata.<br />
<br />
Please note: Ag, Ca, Cd, Cl, Cu, Ge, Hg, K, S, Sn, Tl, V, W and Zn are given as elemental evaluations which are not suitable for many activation analyses.<br />
<br />
For more details we refer the interested reader to the [http://dx.doi.org/10.1051/ndata:07570 ND2007 paper on CENDL-3.1].</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Nuclear_data_forms&diff=877Nuclear data forms2017-03-10T14:58:48Z<p>Michael Fleming: /* Fission Yield Data */</p>
<hr />
<div>FISPACT-II requires connection to several nuclear data libraries and forms before it can be used to calculate inventories. While any libraries in the correct ENDF-6 format could be used (with suitable processing), the development of FISPACT-II over the last several years has run in parallel with the development of the TALYS-based Evaluated Nuclear Data Library TENDL project and those libraries are the recommended source of cross section data forms. Together FISPACT-II and TENDL's nuclear data forms make up the simulation platform that is a complete package tailored for all application needs: nuclear fission and fusion, nuclear fuel cycle, accelerator physics, isotope production, material characterisation, storage and life cycle, earth exploration, astrophysics, homeland security and more. <br />
<br />
=Overview=<br />
<br />
The following data libraries are required:<br />
<br />
# Cross section data for neutron, proton, deuteron, alpha and gamma-induced reactions<br />
# Fission yields data for neutron, proton, deuteron, alpha and gamma-induced reactions<br />
# Variance-covaraiance data for neutron-induced reactions<br />
# Probability tables data for neutron-induced reactions in the resonance energy ranges<br />
# Decay data<br />
# Radiological data:<br />
#* Biological hazard data<br />
#* Legal transport data<br />
#* Clearance data<br />
<br />
To streamline, simplify and control any feature of all the nuclear data assimilation processes, the code development philosophy has been to follow in all aspects as much as possible the format described in the [https://www.bnl.gov/isd/documents/70393.pdf ENDF-6 format manual]. Three processing codes are used in sequence and in parallel to produce, process, check, and compare the nuclear data forms: NJOY12-050, PREPRO-2015 and CALENDF-2010. All the processing steps cannot be handled by only one or even two of those unique processing codes, a combination of the three is needed to extract the data forms that are the most useful in all applications. A schematic of the processing sequences is shown in the figure below. <br />
<br />
=Cross Section Data=<br />
<br />
The principal sources of cross-section data are the di erent generations of the TALYS-based Evaluated Nuclear Data Libraries. The latest TENDL-2015 is the recommended evaluated data source for use in any type of nuclear technology applications. The principal advances of this new library are in the unique target coverage, over 2800 nuclides; the upper energy range, 200 MeV; variance-covariance information for all nuclides; and the extension to cover all important projectiles: neutron, proton, deuteron, alpha and gamma, and last but not least the proven capacity of this type of library to transfer regularly to technology the feedbacks of extensive validation, veri cation and benchmark activities from one release to the next. TENDL is the sixth generation of such a library and as such has bene ted from the previous releases since TENDL-2008, as well as a [http://fispact.ukaea.uk/documentation-2/ wide range of modern V&V].<br />
<br />
The cross sections are provided in a set of group structures including:<br />
<br />
*[[UKAEA-1102 group structure | UKAEA-1102]] general-purpose neutron group structure<br />
*[[CCFE-162 group structure | CCFE-162]] incident charged particle group structure<br />
*[[CCFE-709 group structure | CCFE-709]] fusion neutron group structure<br />
*CASMO-586 fission reactor group structure<br />
*Several legacy groups are available with deprecated EAF libraries<br />
<br />
While the neutron data is contained in the finer 709 and 1102 multi-groups, the 162 scheme for the non-resonant p, d, α and γ-induced cross-sections is used. The data format used is fully compliant with the ENDF-6 manual specification handled on an isotopic basis and so allows many existing utility codes further to manipulate, visualise or check any aspects of the pre-processed files. The data files are produced using a complex but robust, complementary sequence of modules of the processing codes NJOY12-050 and PREPRO-2015. During the processing outputs from veri cation and validation steps are regularly taken in order to establish the validity of all computed derived data. To be able to account for Doppler broadening effects the processed files are given at three reactor temperatures: 293.6, 600 and 900 degree Kelvin and two astrophysical temperatures: 5 and 30 keV.<br />
<br />
=Fission Yield Data=<br />
<br />
The fission yield data need to be provided for each actinide and incident particle. The files are supplied in an ENDF-6 format and are read by FISPACT-II with no further processing. A library is provided based on the JEFF-3.1.1 library for neutron-induced fission. Only 19 of the many nuclides that have ssion have any ssion yield data in JEFF-3.1.1 and these cover only a reduced energy range. For the remainder the UKFY4.2 library then further extends the range before a neighbouring fission yield is used. This UKFY4.2 library using Wahl's systematics is also used for all other particle induced fission yields.<br />
<br />
[http://www.khs-erzhausen.de/GEF.html GEF-based fission-fragment yield libraries] in ENDF-6 format are also provided: GEFY-5.2 as independent and cumulative ssion-fragment yields with multi-chance fission. The uncertainties are given and reflect the uncertainties of the model. They are determined from calculations with perturbed model parameters. 109 spontaneous and 119 neutron induced ssion, including target in isomeric state are provided on a fine 49 incident energy grid structure up to 20 MeV.<br />
<br />
=Variance and Covariance Data=<br />
<br />
Above the upper energy of the resolved resonance range, for each of the 2800+ isotopes a Monte Carlo method in which the covariance data come from uncertainties of the nuclear model calculations is used. A complete description of the procedure is given in [dx.doi.org/10.1016/j.nima.2008.02.003 this reference]. For all isotopes, the initial "best" set of results is produced by a TALYS calculation with an adjusted input parameter set. This set of results is stored in a set of sampeld ENDF files MF-3 to MF-10. For each isotope, many TALYS runs with random nuclear model parameters are performed, which are used to generate and correlations. As well as correlation within the same reaction channels, correlation between reaction channels is included. All information on cross section covariance is stored in the MF-33 format, starting at the end of the resonance range up to 200 MeV. Short-range, self-scaling variance components are also specified for each MT type.<br />
<br />
The data format used to store the variance-covariance information has been made fully compliant with the ENDF-6 format description and the files are read directly by FISPACT-II without any further processing. <br />
<br />
=Probability Tables=<br />
<br />
The CALENDF nuclear data processing system is used to convert the evaluation defining the cross-sections in ENDF-6 format (i.e., the resonance parameters, both resolved and unresolved) into forms useful for applications. Those forms used to describe neutron cross-section uctuations correspond to cross section probability tables", based on Gauss quadratures and e ective cross-sections. The CALENDF-2010 code provides those probability tables in the energy range from 0.1 eV up to the end of the resolved or the unresolved resonance range. Probability table data in 709 group formats are provided for the majority of isotopes of the TENDL library. These data are used to model dilution e ects from channel, isotopic or elemental interferences. To account for Doppler broadening e ects the tables are given at three temperatures: 293.6, 600 and 900 degree Kelvin.<br />
<br />
=Decay Data=<br />
<br />
In addition to cross-sections the other basic quantities required by an inventory code are information on the decay properties (such as half-life) of all the nuclides considered. These data are available in a handful of evaluated decay data libraries. FISPACT-II is able to read the data directly in ENDF-6 format; it requires no pre-processing to be done. The eaf_dec_2010 library, based primarily on the JEFF-3.1.1 and JEF-2.2 radioactive decay data libraries with additional data from the latest UK evaluations UKPADD6.10, contain 2233 nuclides. However, to handle the extension in incident particle type, energy range and number of targets, many more are needed. A new 3875-nuclide decay library UKDD-12 has been assembled from eaf_dec_2010 complemented with all of JEFF-3.1.1, a handful of ENDF/B-VII.1 and other decay files to cover the range of daughters of TENDL and short lived ssion products.<br />
<br />
There remain compatibility issues between the isomer de nitions arising from the cross section library, through the RIPL-3 database and the newly assembled decay library. Historical incompatibilities in isomeric state number (g, m, n, o, . . . ) and energy levels between radionuclide daughter products of reactions and the associated decay data files will need to be addressed in a future release.<br />
<br />
=Other Nuclear Data Libraries=<br />
<br />
FISPACT-II is compatible with all fully ENDF-6 compliant nuclear data forms which have been suitably processed and provided in the required multigroup stuctures. Several libraries are distributed with the code, including the most recent neutron-incident, fission yield and decay data from ENDF/B, JENDL and JEFF. <br />
<br />
==ENDF/B Nuclear Data Libraries==<br />
<br />
The Cross Section Evaluation Working Group (CSEWG) released the ENDF/B-VII.1 library on 22 December 2011. The ENDF/B-VII.1 library is the US latest recommended evaluated nuclear data le for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0, including: many new evaluation in the neutron sublibrary (423 in all) and over 190 of these contain covariances, new ssion product yields for 31 isotopes and a greatly expanded decay data sublibrary for 3817 radionuclides.<br />
<br />
For more details, visit [http://www.nndc.bnl.gov/endf/b7.1/ the NNDC offical website].<br />
<br />
==JENDL Nuclear Data Libraries==<br />
<br />
The purpose of JENDL-4.0 is to provide a Japanese standard library for fast breeder reactors, thermal reactors, fusion neutronics and shielding calculations, and other applications. The data libraries used have been updated to the JENDL-4.0u level of August 2013 for both the neutron reaction and ssion yields sublibrary. JENDL FP Decay Data File 2011 contains decay data of 1284 FP nuclides (of which 142 nuclides are stable) that includes recent TAGS (Total Absorption Gamma-ray Spectroscopy) information.<br />
<br />
For more details, visit [http://wwwndc.jaea.go.jp/jendl/j40/j40.html the JAEA official website].<br />
<br />
==JEFF Nuclear Data Libraries==<br />
<br />
The Joint Evaluated Fission and Fusion File is an evaluated library produced via an international collaboration of Data Bank member countries co-ordinated by the JEFF Scientific Co-ordination Group, under the auspices of the NEA Data Bank. The new JEFF-3.2 general purpose library has been released on March 5, 2014 in ENDF-6 format and contains incident neutron data for 472 nuclides or elements from 1-H-1 to 100-Fm-255.<br />
<br />
For more details, visit [https://www.oecd-nea.org/dbforms/data/eva/evatapes/jeff_32/ the OECD-NEA official website].<br />
<br />
==CENDL Nuclear Data Libraries==<br />
<br />
The CENDL-3.1 neutron-induced cross section data was not released in the most recent FISPACT-II 3.00 version, but is available in the 709 group structure ENDF-6 format files directly from [http://www.ccfe.ac.uk/easy-data/FISPACT-II/ENDFdata/CENDL31data.tgz the FISPACT-II online nuclear data repository]. The compressed file is approximately 26 Mb in size. It is recommended that users install the uncompressed files within their FISPACT-II installation directory under ENDFdata.<br />
<br />
Please note: Ag, Ca, Cd, Cl, Cu, Ge, Hg, K, S, Sn, Tl, V, W and Zn are given as elemental evaluations which are not suitable for many activation analyses.<br />
<br />
For more details we refer the interested reader to the [http://dx.doi.org/10.1051/ndata:07570 ND2007 paper on CENDL-3.1].</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Nuclear_data_forms&diff=876Nuclear data forms2017-03-10T14:58:17Z<p>Michael Fleming: /* Decay Data */</p>
<hr />
<div>FISPACT-II requires connection to several nuclear data libraries and forms before it can be used to calculate inventories. While any libraries in the correct ENDF-6 format could be used (with suitable processing), the development of FISPACT-II over the last several years has run in parallel with the development of the TALYS-based Evaluated Nuclear Data Library TENDL project and those libraries are the recommended source of cross section data forms. Together FISPACT-II and TENDL's nuclear data forms make up the simulation platform that is a complete package tailored for all application needs: nuclear fission and fusion, nuclear fuel cycle, accelerator physics, isotope production, material characterisation, storage and life cycle, earth exploration, astrophysics, homeland security and more. <br />
<br />
=Overview=<br />
<br />
The following data libraries are required:<br />
<br />
# Cross section data for neutron, proton, deuteron, alpha and gamma-induced reactions<br />
# Fission yields data for neutron, proton, deuteron, alpha and gamma-induced reactions<br />
# Variance-covaraiance data for neutron-induced reactions<br />
# Probability tables data for neutron-induced reactions in the resonance energy ranges<br />
# Decay data<br />
# Radiological data:<br />
#* Biological hazard data<br />
#* Legal transport data<br />
#* Clearance data<br />
<br />
To streamline, simplify and control any feature of all the nuclear data assimilation processes, the code development philosophy has been to follow in all aspects as much as possible the format described in the [https://www.bnl.gov/isd/documents/70393.pdf ENDF-6 format manual]. Three processing codes are used in sequence and in parallel to produce, process, check, and compare the nuclear data forms: NJOY12-050, PREPRO-2015 and CALENDF-2010. All the processing steps cannot be handled by only one or even two of those unique processing codes, a combination of the three is needed to extract the data forms that are the most useful in all applications. A schematic of the processing sequences is shown in the figure below. <br />
<br />
=Cross Section Data=<br />
<br />
The principal sources of cross-section data are the di erent generations of the TALYS-based Evaluated Nuclear Data Libraries. The latest TENDL-2015 is the recommended evaluated data source for use in any type of nuclear technology applications. The principal advances of this new library are in the unique target coverage, over 2800 nuclides; the upper energy range, 200 MeV; variance-covariance information for all nuclides; and the extension to cover all important projectiles: neutron, proton, deuteron, alpha and gamma, and last but not least the proven capacity of this type of library to transfer regularly to technology the feedbacks of extensive validation, veri cation and benchmark activities from one release to the next. TENDL is the sixth generation of such a library and as such has bene ted from the previous releases since TENDL-2008, as well as a [http://fispact.ukaea.uk/documentation-2/ wide range of modern V&V].<br />
<br />
The cross sections are provided in a set of group structures including:<br />
<br />
*[[UKAEA-1102 group structure | UKAEA-1102]] general-purpose neutron group structure<br />
*[[CCFE-162 group structure | CCFE-162]] incident charged particle group structure<br />
*[[CCFE-709 group structure | CCFE-709]] fusion neutron group structure<br />
*CASMO-586 fission reactor group structure<br />
*Several legacy groups are available with deprecated EAF libraries<br />
<br />
While the neutron data is contained in the finer 709 and 1102 multi-groups, the 162 scheme for the non-resonant p, d, α and γ-induced cross-sections is used. The data format used is fully compliant with the ENDF-6 manual specification handled on an isotopic basis and so allows many existing utility codes further to manipulate, visualise or check any aspects of the pre-processed files. The data files are produced using a complex but robust, complementary sequence of modules of the processing codes NJOY12-050 and PREPRO-2015. During the processing outputs from veri cation and validation steps are regularly taken in order to establish the validity of all computed derived data. To be able to account for Doppler broadening effects the processed files are given at three reactor temperatures: 293.6, 600 and 900 degree Kelvin and two astrophysical temperatures: 5 and 30 keV.<br />
<br />
=Fission Yield Data=<br />
<br />
The fission yield data need to be provided for each actinide and incident particle. The files are supplied in an ENDF-6 format and are read by FISPACT-II with no further processing. A library is provided based on the JEFF-3.1.1 library for neutron-induced fission. Only 19 of the many nuclides that have ssion have any ssion yield data in JEFF-3.1.1 and these cover only a reduced energy range. For the remainder the UKFY4.2 library then further extends the range before a neighbouring fission yield is used. This UKFY4.2 library using Wahl's systematics is also used for all other particle induced fission yields.<br />
<br />
[http://www.khs-erzhausen.de/GEF.html GEF-based fission-fragment yield libraries] in ENDF-6 format are also provided: GEFY-5.2 as independent and cumulative ssion-fragment yields with multi-chance fission. The uncertainties are given and re ect the uncertainties of the model. They are determined from calculations with perturbed model parameters. 109 spontaneous and 119 neutron induced ssion, including target in isomeric state are provided on a fine 49 incident energy grid structure up to 20 MeV. <br />
<br />
=Variance and Covariance Data=<br />
<br />
Above the upper energy of the resolved resonance range, for each of the 2800+ isotopes a Monte Carlo method in which the covariance data come from uncertainties of the nuclear model calculations is used. A complete description of the procedure is given in [dx.doi.org/10.1016/j.nima.2008.02.003 this reference]. For all isotopes, the initial "best" set of results is produced by a TALYS calculation with an adjusted input parameter set. This set of results is stored in a set of sampeld ENDF files MF-3 to MF-10. For each isotope, many TALYS runs with random nuclear model parameters are performed, which are used to generate and correlations. As well as correlation within the same reaction channels, correlation between reaction channels is included. All information on cross section covariance is stored in the MF-33 format, starting at the end of the resonance range up to 200 MeV. Short-range, self-scaling variance components are also specified for each MT type.<br />
<br />
The data format used to store the variance-covariance information has been made fully compliant with the ENDF-6 format description and the files are read directly by FISPACT-II without any further processing. <br />
<br />
=Probability Tables=<br />
<br />
The CALENDF nuclear data processing system is used to convert the evaluation defining the cross-sections in ENDF-6 format (i.e., the resonance parameters, both resolved and unresolved) into forms useful for applications. Those forms used to describe neutron cross-section uctuations correspond to cross section probability tables", based on Gauss quadratures and e ective cross-sections. The CALENDF-2010 code provides those probability tables in the energy range from 0.1 eV up to the end of the resolved or the unresolved resonance range. Probability table data in 709 group formats are provided for the majority of isotopes of the TENDL library. These data are used to model dilution e ects from channel, isotopic or elemental interferences. To account for Doppler broadening e ects the tables are given at three temperatures: 293.6, 600 and 900 degree Kelvin.<br />
<br />
=Decay Data=<br />
<br />
In addition to cross-sections the other basic quantities required by an inventory code are information on the decay properties (such as half-life) of all the nuclides considered. These data are available in a handful of evaluated decay data libraries. FISPACT-II is able to read the data directly in ENDF-6 format; it requires no pre-processing to be done. The eaf_dec_2010 library, based primarily on the JEFF-3.1.1 and JEF-2.2 radioactive decay data libraries with additional data from the latest UK evaluations UKPADD6.10, contain 2233 nuclides. However, to handle the extension in incident particle type, energy range and number of targets, many more are needed. A new 3875-nuclide decay library UKDD-12 has been assembled from eaf_dec_2010 complemented with all of JEFF-3.1.1, a handful of ENDF/B-VII.1 and other decay files to cover the range of daughters of TENDL and short lived ssion products.<br />
<br />
There remain compatibility issues between the isomer de nitions arising from the cross section library, through the RIPL-3 database and the newly assembled decay library. Historical incompatibilities in isomeric state number (g, m, n, o, . . . ) and energy levels between radionuclide daughter products of reactions and the associated decay data files will need to be addressed in a future release.<br />
<br />
=Other Nuclear Data Libraries=<br />
<br />
FISPACT-II is compatible with all fully ENDF-6 compliant nuclear data forms which have been suitably processed and provided in the required multigroup stuctures. Several libraries are distributed with the code, including the most recent neutron-incident, fission yield and decay data from ENDF/B, JENDL and JEFF. <br />
<br />
==ENDF/B Nuclear Data Libraries==<br />
<br />
The Cross Section Evaluation Working Group (CSEWG) released the ENDF/B-VII.1 library on 22 December 2011. The ENDF/B-VII.1 library is the US latest recommended evaluated nuclear data le for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0, including: many new evaluation in the neutron sublibrary (423 in all) and over 190 of these contain covariances, new ssion product yields for 31 isotopes and a greatly expanded decay data sublibrary for 3817 radionuclides.<br />
<br />
For more details, visit [http://www.nndc.bnl.gov/endf/b7.1/ the NNDC offical website].<br />
<br />
==JENDL Nuclear Data Libraries==<br />
<br />
The purpose of JENDL-4.0 is to provide a Japanese standard library for fast breeder reactors, thermal reactors, fusion neutronics and shielding calculations, and other applications. The data libraries used have been updated to the JENDL-4.0u level of August 2013 for both the neutron reaction and ssion yields sublibrary. JENDL FP Decay Data File 2011 contains decay data of 1284 FP nuclides (of which 142 nuclides are stable) that includes recent TAGS (Total Absorption Gamma-ray Spectroscopy) information.<br />
<br />
For more details, visit [http://wwwndc.jaea.go.jp/jendl/j40/j40.html the JAEA official website].<br />
<br />
==JEFF Nuclear Data Libraries==<br />
<br />
The Joint Evaluated Fission and Fusion File is an evaluated library produced via an international collaboration of Data Bank member countries co-ordinated by the JEFF Scientific Co-ordination Group, under the auspices of the NEA Data Bank. The new JEFF-3.2 general purpose library has been released on March 5, 2014 in ENDF-6 format and contains incident neutron data for 472 nuclides or elements from 1-H-1 to 100-Fm-255.<br />
<br />
For more details, visit [https://www.oecd-nea.org/dbforms/data/eva/evatapes/jeff_32/ the OECD-NEA official website].<br />
<br />
==CENDL Nuclear Data Libraries==<br />
<br />
The CENDL-3.1 neutron-induced cross section data was not released in the most recent FISPACT-II 3.00 version, but is available in the 709 group structure ENDF-6 format files directly from [http://www.ccfe.ac.uk/easy-data/FISPACT-II/ENDFdata/CENDL31data.tgz the FISPACT-II online nuclear data repository]. The compressed file is approximately 26 Mb in size. It is recommended that users install the uncompressed files within their FISPACT-II installation directory under ENDFdata.<br />
<br />
Please note: Ag, Ca, Cd, Cl, Cu, Ge, Hg, K, S, Sn, Tl, V, W and Zn are given as elemental evaluations which are not suitable for many activation analyses.<br />
<br />
For more details we refer the interested reader to the [http://dx.doi.org/10.1051/ndata:07570 ND2007 paper on CENDL-3.1].</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Nuclear_data_forms&diff=875Nuclear data forms2017-03-10T14:57:46Z<p>Michael Fleming: /* Cross Section Data */</p>
<hr />
<div>FISPACT-II requires connection to several nuclear data libraries and forms before it can be used to calculate inventories. While any libraries in the correct ENDF-6 format could be used (with suitable processing), the development of FISPACT-II over the last several years has run in parallel with the development of the TALYS-based Evaluated Nuclear Data Library TENDL project and those libraries are the recommended source of cross section data forms. Together FISPACT-II and TENDL's nuclear data forms make up the simulation platform that is a complete package tailored for all application needs: nuclear fission and fusion, nuclear fuel cycle, accelerator physics, isotope production, material characterisation, storage and life cycle, earth exploration, astrophysics, homeland security and more. <br />
<br />
=Overview=<br />
<br />
The following data libraries are required:<br />
<br />
# Cross section data for neutron, proton, deuteron, alpha and gamma-induced reactions<br />
# Fission yields data for neutron, proton, deuteron, alpha and gamma-induced reactions<br />
# Variance-covaraiance data for neutron-induced reactions<br />
# Probability tables data for neutron-induced reactions in the resonance energy ranges<br />
# Decay data<br />
# Radiological data:<br />
#* Biological hazard data<br />
#* Legal transport data<br />
#* Clearance data<br />
<br />
To streamline, simplify and control any feature of all the nuclear data assimilation processes, the code development philosophy has been to follow in all aspects as much as possible the format described in the [https://www.bnl.gov/isd/documents/70393.pdf ENDF-6 format manual]. Three processing codes are used in sequence and in parallel to produce, process, check, and compare the nuclear data forms: NJOY12-050, PREPRO-2015 and CALENDF-2010. All the processing steps cannot be handled by only one or even two of those unique processing codes, a combination of the three is needed to extract the data forms that are the most useful in all applications. A schematic of the processing sequences is shown in the figure below. <br />
<br />
=Cross Section Data=<br />
<br />
The principal sources of cross-section data are the di erent generations of the TALYS-based Evaluated Nuclear Data Libraries. The latest TENDL-2015 is the recommended evaluated data source for use in any type of nuclear technology applications. The principal advances of this new library are in the unique target coverage, over 2800 nuclides; the upper energy range, 200 MeV; variance-covariance information for all nuclides; and the extension to cover all important projectiles: neutron, proton, deuteron, alpha and gamma, and last but not least the proven capacity of this type of library to transfer regularly to technology the feedbacks of extensive validation, veri cation and benchmark activities from one release to the next. TENDL is the sixth generation of such a library and as such has bene ted from the previous releases since TENDL-2008, as well as a [http://fispact.ukaea.uk/documentation-2/ wide range of modern V&V].<br />
<br />
The cross sections are provided in a set of group structures including:<br />
<br />
*[[UKAEA-1102 group structure | UKAEA-1102]] general-purpose neutron group structure<br />
*[[CCFE-162 group structure | CCFE-162]] incident charged particle group structure<br />
*[[CCFE-709 group structure | CCFE-709]] fusion neutron group structure<br />
*CASMO-586 fission reactor group structure<br />
*Several legacy groups are available with deprecated EAF libraries<br />
<br />
While the neutron data is contained in the finer 709 and 1102 multi-groups, the 162 scheme for the non-resonant p, d, α and γ-induced cross-sections is used. The data format used is fully compliant with the ENDF-6 manual specification handled on an isotopic basis and so allows many existing utility codes further to manipulate, visualise or check any aspects of the pre-processed files. The data files are produced using a complex but robust, complementary sequence of modules of the processing codes NJOY12-050 and PREPRO-2015. During the processing outputs from veri cation and validation steps are regularly taken in order to establish the validity of all computed derived data. To be able to account for Doppler broadening effects the processed files are given at three reactor temperatures: 293.6, 600 and 900 degree Kelvin and two astrophysical temperatures: 5 and 30 keV.<br />
<br />
=Fission Yield Data=<br />
<br />
The fission yield data need to be provided for each actinide and incident particle. The files are supplied in an ENDF-6 format and are read by FISPACT-II with no further processing. A library is provided based on the JEFF-3.1.1 library for neutron-induced fission. Only 19 of the many nuclides that have ssion have any ssion yield data in JEFF-3.1.1 and these cover only a reduced energy range. For the remainder the UKFY4.2 library then further extends the range before a neighbouring fission yield is used. This UKFY4.2 library using Wahl's systematics is also used for all other particle induced fission yields.<br />
<br />
[http://www.khs-erzhausen.de/GEF.html GEF-based fission-fragment yield libraries] in ENDF-6 format are also provided: GEFY-5.2 as independent and cumulative ssion-fragment yields with multi-chance fission. The uncertainties are given and re ect the uncertainties of the model. They are determined from calculations with perturbed model parameters. 109 spontaneous and 119 neutron induced ssion, including target in isomeric state are provided on a fine 49 incident energy grid structure up to 20 MeV. <br />
<br />
=Variance and Covariance Data=<br />
<br />
Above the upper energy of the resolved resonance range, for each of the 2800+ isotopes a Monte Carlo method in which the covariance data come from uncertainties of the nuclear model calculations is used. A complete description of the procedure is given in [dx.doi.org/10.1016/j.nima.2008.02.003 this reference]. For all isotopes, the initial "best" set of results is produced by a TALYS calculation with an adjusted input parameter set. This set of results is stored in a set of sampeld ENDF files MF-3 to MF-10. For each isotope, many TALYS runs with random nuclear model parameters are performed, which are used to generate and correlations. As well as correlation within the same reaction channels, correlation between reaction channels is included. All information on cross section covariance is stored in the MF-33 format, starting at the end of the resonance range up to 200 MeV. Short-range, self-scaling variance components are also specified for each MT type.<br />
<br />
The data format used to store the variance-covariance information has been made fully compliant with the ENDF-6 format description and the files are read directly by FISPACT-II without any further processing. <br />
<br />
=Probability Tables=<br />
<br />
The CALENDF nuclear data processing system is used to convert the evaluation defining the cross-sections in ENDF-6 format (i.e., the resonance parameters, both resolved and unresolved) into forms useful for applications. Those forms used to describe neutron cross-section uctuations correspond to cross section probability tables", based on Gauss quadratures and e ective cross-sections. The CALENDF-2010 code provides those probability tables in the energy range from 0.1 eV up to the end of the resolved or the unresolved resonance range. Probability table data in 709 group formats are provided for the majority of isotopes of the TENDL library. These data are used to model dilution e ects from channel, isotopic or elemental interferences. To account for Doppler broadening e ects the tables are given at three temperatures: 293.6, 600 and 900 degree Kelvin.<br />
<br />
=Decay Data=<br />
<br />
In addition to cross-sections the other basic quantities required by an inventory code are information on the decay properties (such as half-life) of all the nuclides considered. These data are available in a handful of evaluated decay data libraries. FISPACT-II is able to read the data directly in ENDF-6 format; it requires no pre-processing to be done. The eaf_dec_2010 library, based primarily on the JEFF-3.1.1 and JEF-2.2 radioactive decay data libraries with additional data from the latest UK evaluations UKPADD6.10, contain 2233 nuclides. However, to handle the extension in incident particle type, energy range and number of targets, many more are needed. A new 3875-nuclide decay library UKDD-12 has been assembled from eaf_dec_2010 complemented with all of JEFF-3.1.1, a handful of ENDF/B-VII.1 and other decay les to cover the range of daughters of TENDL and short lived ssion products.<br />
<br />
There remain compatibility issues between the isomer de nitions arising from the cross section library, through the RIPL-3 database and the newly assembled decay library. Historical incompatibilities in isomeric state number (g, m, n, o, . . . ) and energy levels between radionuclide daughter products of reactions and the associated decay data les will need to be addressed in a future release.<br />
<br />
<br />
=Other Nuclear Data Libraries=<br />
<br />
FISPACT-II is compatible with all fully ENDF-6 compliant nuclear data forms which have been suitably processed and provided in the required multigroup stuctures. Several libraries are distributed with the code, including the most recent neutron-incident, fission yield and decay data from ENDF/B, JENDL and JEFF. <br />
<br />
==ENDF/B Nuclear Data Libraries==<br />
<br />
The Cross Section Evaluation Working Group (CSEWG) released the ENDF/B-VII.1 library on 22 December 2011. The ENDF/B-VII.1 library is the US latest recommended evaluated nuclear data le for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0, including: many new evaluation in the neutron sublibrary (423 in all) and over 190 of these contain covariances, new ssion product yields for 31 isotopes and a greatly expanded decay data sublibrary for 3817 radionuclides.<br />
<br />
For more details, visit [http://www.nndc.bnl.gov/endf/b7.1/ the NNDC offical website].<br />
<br />
==JENDL Nuclear Data Libraries==<br />
<br />
The purpose of JENDL-4.0 is to provide a Japanese standard library for fast breeder reactors, thermal reactors, fusion neutronics and shielding calculations, and other applications. The data libraries used have been updated to the JENDL-4.0u level of August 2013 for both the neutron reaction and ssion yields sublibrary. JENDL FP Decay Data File 2011 contains decay data of 1284 FP nuclides (of which 142 nuclides are stable) that includes recent TAGS (Total Absorption Gamma-ray Spectroscopy) information.<br />
<br />
For more details, visit [http://wwwndc.jaea.go.jp/jendl/j40/j40.html the JAEA official website].<br />
<br />
==JEFF Nuclear Data Libraries==<br />
<br />
The Joint Evaluated Fission and Fusion File is an evaluated library produced via an international collaboration of Data Bank member countries co-ordinated by the JEFF Scientific Co-ordination Group, under the auspices of the NEA Data Bank. The new JEFF-3.2 general purpose library has been released on March 5, 2014 in ENDF-6 format and contains incident neutron data for 472 nuclides or elements from 1-H-1 to 100-Fm-255.<br />
<br />
For more details, visit [https://www.oecd-nea.org/dbforms/data/eva/evatapes/jeff_32/ the OECD-NEA official website].<br />
<br />
==CENDL Nuclear Data Libraries==<br />
<br />
The CENDL-3.1 neutron-induced cross section data was not released in the most recent FISPACT-II 3.00 version, but is available in the 709 group structure ENDF-6 format files directly from [http://www.ccfe.ac.uk/easy-data/FISPACT-II/ENDFdata/CENDL31data.tgz the FISPACT-II online nuclear data repository]. The compressed file is approximately 26 Mb in size. It is recommended that users install the uncompressed files within their FISPACT-II installation directory under ENDFdata.<br />
<br />
Please note: Ag, Ca, Cd, Cl, Cu, Ge, Hg, K, S, Sn, Tl, V, W and Zn are given as elemental evaluations which are not suitable for many activation analyses.<br />
<br />
For more details we refer the interested reader to the [http://dx.doi.org/10.1051/ndata:07570 ND2007 paper on CENDL-3.1].</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Reference_input_spectra&diff=872Reference input spectra2017-03-10T14:07:59Z<p>Michael Fleming: </p>
<hr />
<div>__NOTOC__<br />
<br />
The collapsed cross-sections depend strongly on the nature of the projectile spectra, and so it is important to use the appropriate spectrum together with the appropriately-weighted cross-section data. With the advances of modern simulation software and high resolution spectra the user is reminded of the importance of the tails, low or high-energy ones, on the reaction rates.<br />
<br />
The majority of neutron-application spectra stem from light-water assemblies, mock-ups or reactors where the integral responses are strongly, if not solely, influenced by the energy ranges of the fission spectra and thermal maxwellian. Fusion spectra that have been obtained from magnetic confinement (MCF) or inertial confinement fusion (ICF) present typical D-D 2.5 MeV, or D-T 14 MeV peaks sometimes accompanied by a higher-energy tail, but also showing rather different slowing-down profiles. Accelerator-driven beam spectra are important in their role in nuclear data acquisition and materials research, but also for medical therapeutic and diagnostic applications.<br />
<br />
In essence the particle spectrum profile, through the collapsing process, emphasises the energy region of most importance for each application. Transferring data from one application or energy range to another should be done with great care as it can easily lead to misleading and inappropriate numerical results.<br />
<br />
Several incident particle spectra are provided in the table below, mostly including neutron incident spectra but with some charged particle spectra. '''Note''' that these are provided in the original energy group structures as generated by the code(s) that calculated them. These are often ''not'' the same energy group structures as those provided for e.g. the TENDL nuclear data libraries and require a flux conversion using [[Keyword:GRPCONVERT | '''GRPCONVERT''']]. Note that while the group conversion can easily be performed, this cannot add structure when moving to a refined group structure when moving to a more refined multi-group.<br />
<br />
Each of the spectra below is provided in the format of an arbitrary flux <tt>arb_flux</tt> file for reading in the '''GRPCONVERT''' module as well as a figure showing the spectrum in flux per unit lethargy using an arbitrary normalisation. For convenience, all of the <tt>arb_flux</tt> files are available in the table below.<br />
<br />
<br />
{| class="wikitable sortable" <br />
|+ Reference incident particle spectra<br />
! Name<br />
! Group<br />
! Particle<br />
! <tt>arb_flux</tt> file<br />
! Figure<br />
! Description<br />
|-<br />
| Bigten<br />
| 407<br />
| n<br />
| [[Media:407 Bigten.txt]]<br />
| [[Reference_input_spectra#Bigten | Bigten]]<br />
| <br />
|-<br />
| BWR-MOX-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-0.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-0 | BWR-MOX-Gd-0]]<br />
| <br />
|-<br />
| BWR-MOX-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-15.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-15 | BWR-MOX-Gd-15]]<br />
| <br />
|-<br />
| BWR-MOX-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-40.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-40 | BWR-MOX-Gd-40]]<br />
| <br />
|-<br />
| BWR-RPV<br />
| 198<br />
| n<br />
| [[Media:198 BWR-RPV.txt]]<br />
| [[Reference_input_spectra#BWR-RPV | BWR-RPV]]<br />
| <br />
|-<br />
| BWR-UO2-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-0.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-0 | BWR-UO2-Gd-0]]<br />
| <br />
|-<br />
| BWR-UO2-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-15.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-15 | BWR-UO2-Gd-15]]<br />
| <br />
|-<br />
| BWR-UO2-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-40.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-40 | BWR-UO2-Gd-40]]<br />
| <br />
|-<br />
| CERN-H4IRRAD<br />
| 288<br />
| n<br />
| [[Media:288 CERN-H4IRRAD.txt]]<br />
| [[Reference_input_spectra#CERN-H4IRRAD | CERN-H4IRRAD]]<br />
| <br />
|-<br />
| Cf252<br />
| 070<br />
| n<br />
| [[Media:070 Cf252.txt]]<br />
| [[Reference_input_spectra#Cf252 | Cf252]]<br />
| <br />
|-<br />
| DEMO-HCPB-BP<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-BP.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-BP | DEMO-HCPB-BP]]<br />
| <br />
|-<br />
| DEMO-HCPB-FW<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-FW.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-FW | DEMO-HCPB-FW]]<br />
| <br />
|-<br />
| DEMO-HCPB-VV<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-VV.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-VV | DEMO-HCPB-VV]]<br />
| <br />
|-<br />
| EBR-2<br />
| 029<br />
| n<br />
| [[Media:029 EBR-2.txt]]<br />
| [[Reference_input_spectra#EBR-2 | EBR-2]]<br />
| <br />
|-<br />
| Frascati-NG<br />
| 175<br />
| n<br />
| [[Media:175 Frascati-NG.txt]]<br />
| [[Reference_input_spectra#Frascati-NG | Frascati-NG]]<br />
| <br />
|-<br />
| HCLL-FW<br />
| 616<br />
| n<br />
| [[Media:616 HCLL-FW.txt]]<br />
| [[Reference_input_spectra#HCLL-FW | HCLL-FW]]<br />
| <br />
|-<br />
| HCLL-VV<br />
| 616<br />
| n<br />
| [[Media:616 HCLL-VV.txt]]<br />
| [[Reference_input_spectra#HCLL-VV | HCLL-VV]]<br />
| <br />
|-<br />
| HCPB-FW<br />
| 616<br />
| n<br />
| [[Media:616 HCPB-FW.txt]]<br />
| [[Reference_input_spectra#HCPB-FW | HCPB-FW]]<br />
| <br />
|-<br />
| HCPB-VV<br />
| 616<br />
| n<br />
| [[Media:616 HCPB-VV.txt]]<br />
| [[Reference_input_spectra#HCPB-VV | HCPB-VV]]<br />
| <br />
|-<br />
| HFIR-highres<br />
| 238<br />
| n<br />
| [[Media:238 HFIR-highres.txt]]<br />
| [[Reference_input_spectra#HFIR-highres | HFIR-highres]]<br />
| <br />
|-<br />
| HFIR-lowres<br />
| 100<br />
| n<br />
| [[Media:100 HFIR-lowres.txt]]<br />
| [[Reference_input_spectra#HFIR-lowres | HFIR-lowres]]<br />
| <br />
|-<br />
| HFIR-VXF3-AD<br />
| 238<br />
| n<br />
| [[Media:238 HFIR-VXF3-AD.txt]]<br />
| [[Reference_input_spectra#HFIR-VXF3-AD | HFIR-VXF3-AD]]<br />
| <br />
|-<br />
| HFR-high<br />
| 616<br />
| n<br />
| [[Media:616 HFR-high.txt]]<br />
| [[Reference_input_spectra#HFR-high | HFR-high]]<br />
| <br />
|-<br />
| HFR-low<br />
| 616<br />
| n<br />
| [[Media:616 HFR-low.txt]]<br />
| [[Reference_input_spectra#HFR-low | HFR-low]]<br />
| <br />
|-<br />
| IFMIF-DLi<br />
| 211<br />
| n<br />
| [[Media:211 IFMIF-DLi.txt]]<br />
| [[Reference_input_spectra#IFMIF-DLi | IFMIF-DLi]]<br />
| <br />
|-<br />
| ITER-DD<br />
| 175<br />
| n<br />
| [[Media:175 ITER-DD.txt]]<br />
| [[Reference_input_spectra#ITER-DD | ITER-DD]]<br />
| <br />
|-<br />
| ITER-DT<br />
| 175<br />
| n<br />
| [[Media:175 ITER-DT.txt]]<br />
| [[Reference_input_spectra#ITER-DT | ITER-DT]]<br />
| <br />
|-<br />
| JAEA-FNS<br />
| 175<br />
| n<br />
| [[Media:175 JAEA-FNS.txt]]<br />
| [[Reference_input_spectra#JAEA-FNS | JAEA-FNS]]<br />
| <br />
|-<br />
| JET-FW<br />
| 100<br />
| n<br />
| [[Media:100 JET-FW.txt]]<br />
| [[Reference_input_spectra#JET-FW | JET-FW]]<br />
| <br />
|-<br />
| LMJ-g<br />
| 161<br />
| γ<br />
| [[Media:161 LMJ-g.txt]]<br />
| [[Reference_input_spectra#LMJ-g | LMJ-g]]<br />
| <br />
|-<br />
| Maxwellians<br />
| 709<br />
| n<br />
| [[Media:709 Maxwellian-1keV.txt | 1 keV]] [[Media:709 Maxwellian-5keV.txt | 5 keV]] [[Media:709 Maxwellian-10keV.txt | 10 keV]] [[Media:709 Maxwellian-30keV.txt | 30 keV]] [[Media:709 Maxwellian-80keV.txt | 80 keV]]<br />
| [[Reference_input_spectra#Maxwellians | Maxwellians]]<br />
| <br />
|-<br />
| NIF-ignition<br />
| 150<br />
| n<br />
| [[Media:150 NIF-ignition.txt]]<br />
| [[Reference_input_spectra#NIF-ignition | NIF-ignition]]<br />
| <br />
|-<br />
| Paluel<br />
| 172<br />
| n<br />
| [[Media:172 Paluel.txt]]<br />
| [[Reference_input_spectra#Paluel | Paluel]]<br />
| <br />
|-<br />
| Phenix<br />
| 172<br />
| n<br />
| [[Media:172 Phenix.txt]]<br />
| [[Reference_input_spectra#Phenix | Phenix]]<br />
| <br />
|-<br />
| PWR-MOX-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-0.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-0 | PWR-MOX-0]]<br />
| <br />
|-<br />
| PWR-MOX-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-15.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-15 | PWR-MOX-15]]<br />
| <br />
|-<br />
| PWR-MOX-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-40.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-40 | PWR-MOX-40]]<br />
| <br />
|-<br />
| PWR-RPV<br />
| 198<br />
| n<br />
| [[Media:198 PWR-RPV.txt]]<br />
| [[Reference_input_spectra#PWR-RPV | PWR-RPV]]<br />
| <br />
|-<br />
| PWR-UO2-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-0.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-0 | PWR-UO2-0]]<br />
| <br />
|-<br />
| PWR-UO2-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-15.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-15 | PWR-UO2-15]]<br />
| <br />
|-<br />
| PWR-UO2-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-40.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-40 | PWR-UO2-40]]<br />
| <br />
|-<br />
| PWR-UO2-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-0.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-0 | PWR-UO2-Gd-0]]<br />
| <br />
|-<br />
| PWR-UO2-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-15.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-15 | PWR-UO2-Gd-15]]<br />
| <br />
|-<br />
| PWR-UO2-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-40.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-40 | PWR-UO2-Gd-40]]<br />
| <br />
|-<br />
| Superphenix<br />
| 172<br />
| n<br />
| [[Media:172 Superphenix.txt]]<br />
| [[Reference_input_spectra#Superphenix | Superphenix]]<br />
| <br />
|-<br />
| TUD-NG<br />
| 175<br />
| n<br />
| [[Media:175 TUD-NG.txt]]<br />
| [[Reference_input_spectra#TUD-NG | TUD-NG]]<br />
| <br />
|-<br />
| WCCB-FW<br />
| 616<br />
| n<br />
| [[Media:616 WCCB-FW.txt]]<br />
| [[Reference_input_spectra#WCCB-FW | WCCB-FW]]<br />
| <br />
|-<br />
| WCCB-VV<br />
| 616<br />
| n<br />
| [[Media:616 WCCB-VV.txt]]<br />
| [[Reference_input_spectra#WCCB-VV | WCCB-VV]]<br />
| <br />
|-<br />
| WCLL-FW<br />
| 616<br />
| n<br />
| [[Media:616 WCLL-FW.txt]]<br />
| [[Reference_input_spectra#WCLL-FW | WCLL-FW]]<br />
| <br />
|-<br />
| WCLL-VV<br />
| 616<br />
| n<br />
| [[Media:616 WCLL-VV.txt]]<br />
| [[Reference_input_spectra#WCLL-VV | WCLL-VV]]<br />
| <br />
|}<br />
<br />
<br />
==Bigten==<br />
<br />
[[File:407 Bigten.png|550px|center|thumb|alt=Spectrum|[[Media:407 Bigten.txt]]]]<br />
<br />
==BWR-MOX-Gd-0==<br />
<br />
[[File:1102 BWR-MOX-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-0.txt]]]]<br />
<br />
==BWR-MOX-Gd-15==<br />
<br />
[[File:1102 BWR-MOX-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-15.txt]]]]<br />
<br />
==BWR-MOX-Gd-40==<br />
<br />
[[File:1102 BWR-MOX-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-40.txt]]]]<br />
<br />
==BWR-RPV==<br />
<br />
[[File:198 BWR-RPV.png|550px|center|thumb|alt=Spectrum|[[Media:198 BWR-RPV.txt]]]]<br />
<br />
==BWR-UO2-Gd-0==<br />
<br />
[[File:1102 BWR-UO2-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-0.txt]]]]<br />
<br />
==BWR-UO2-Gd-15==<br />
<br />
[[File:1102 BWR-UO2-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-15.txt]]]]<br />
<br />
==BWR-UO2-Gd-40==<br />
<br />
[[File:1102 BWR-UO2-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-40.txt]]]]<br />
<br />
==CERN-H4IRRAD==<br />
<br />
[[File:288 CERN-H4IRRAD.png|550px|center|thumb|alt=Spectrum|[[Media:288 CERN-H4IRRAD.txt]]]]<br />
<br />
==Cf252==<br />
<br />
[[File:070 Cf252.png|550px|center|thumb|alt=Spectrum|[[Media:070 Cf252.txt]]]]<br />
<br />
==DEMO-HCPB-BP==<br />
<br />
[[File:616 DEMO-HCPB-BP.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-BP.txt]]]]<br />
<br />
==DEMO-HCPB-FW==<br />
<br />
[[File:616 DEMO-HCPB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-FW.txt]]]]<br />
<br />
==DEMO-HCPB-VV==<br />
<br />
[[File:616 DEMO-HCPB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-VV.txt]]]]<br />
<br />
==EBR-2==<br />
<br />
[[File:029 EBR-2.png|550px|center|thumb|alt=Spectrum|[[Media:029 EBR-2.txt]]]]<br />
<br />
==Frascati-NG==<br />
<br />
[[File:175 Frascati-NG.png|550px|center|thumb|alt=Spectrum|[[Media:175 Frascati-NG.txt]]]]<br />
<br />
==HCLL-FW==<br />
<br />
[[File:616 HCLL-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCLL-FW.txt]]]]<br />
<br />
==HCLL-VV==<br />
<br />
[[File:616 HCLL-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCLL-VV.txt]]]]<br />
<br />
==HCPB-FW==<br />
<br />
[[File:616 HCPB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCPB-FW.txt]]]]<br />
<br />
==HCPB-VV==<br />
<br />
[[File:616 HCPB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCPB-VV.txt]]]]<br />
<br />
==HFIR-highres==<br />
<br />
[[File:238 HFIR-highres.png|550px|center|thumb|alt=Spectrum|[[Media:238 HFIR-highres.txt]]]]<br />
<br />
==HFIR-lowres==<br />
<br />
[[File:100 HFIR-lowres.png|550px|center|thumb|alt=Spectrum|[[Media:100 HFIR-lowres.txt]]]]<br />
<br />
==HFIR-VXF3-AD==<br />
<br />
[[File:238 HFIR-VXF3-AD.png|550px|center|thumb|alt=Spectrum|[[Media:238 HFIR-VXF3-AD.txt]]]]<br />
<br />
==HFR-high==<br />
<br />
[[File:616 HFR-high.png|550px|center|thumb|alt=Spectrum|[[Media:616 HFR-high.txt]]]]<br />
<br />
==HFR-low==<br />
<br />
[[File:616 HFR-low.png|550px|center|thumb|alt=Spectrum|[[Media:616 HFR-low.txt]]]]<br />
<br />
==IFMIF-DLi==<br />
<br />
[[File:211 IFMIF-DLi.png|550px|center|thumb|alt=Spectrum|[[Media:211 IFMIF-DLi.txt]]]]<br />
<br />
==ITER-DD==<br />
<br />
[[File:175 ITER-DD.png|550px|center|thumb|alt=Spectrum|[[Media:175 ITER-DD.txt]]]]<br />
<br />
==ITER-DT==<br />
<br />
[[File:175 ITER-DT.png|550px|center|thumb|alt=Spectrum|[[Media:175 ITER-DT.txt]]]]<br />
<br />
==JAEA-FNS==<br />
<br />
[[File:175 JAEA-FNS.png|550px|center|thumb|alt=Spectrum|[[Media:175 JAEA-FNS.txt]]]]<br />
<br />
==JET-FW==<br />
<br />
[[File:100 JET-FW.png|550px|center|thumb|alt=Spectrum|[[Media:100 JET-FW.txt]]]]<br />
<br />
==LMJ-g==<br />
<br />
[[File:161 LMJ-g.png|550px|center|thumb|alt=Spectrum|[[Media:161 LMJ-g.txt]]]]<br />
<br />
==Maxwellians==<br />
<br />
[[File:709 Maxwellian.png|550px|center|thumb|alt=Spectrum|[[Media:709 Maxwellian-1keV.txt | 1 keV]] [[Media:709 Maxwellian-5keV.txt | 5 keV]] [[Media:709 Maxwellian-10keV.txt | 10 keV]] [[Media:709 Maxwellian-30keV.txt | 30 keV]] [[Media:709 Maxwellian-80keV.txt | 80 keV]]]]<br />
<br />
==NIF-ignition==<br />
<br />
[[File:150 NIF-ignition.png|550px|center|thumb|alt=Spectrum|[[Media:150 NIF-ignition.txt]]]]<br />
<br />
==Paluel==<br />
<br />
[[File:172 Paluel.png|550px|center|thumb|alt=Spectrum|[[Media:172 Paluel.txt]]]]<br />
<br />
==Phenix==<br />
<br />
[[File:172 Phenix.png|550px|center|thumb|alt=Spectrum|[[Media:172 Phenix.txt]]]]<br />
<br />
==PWR-MOX-0==<br />
<br />
[[File:1102 PWR-MOX-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-0.txt]]]]<br />
<br />
==PWR-MOX-15==<br />
<br />
[[File:1102 PWR-MOX-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-15.txt]]]]<br />
<br />
==PWR-MOX-40==<br />
<br />
[[File:1102 PWR-MOX-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-40.txt]]]]<br />
<br />
==PWR-RPV==<br />
<br />
[[File:198 PWR-RPV.png|550px|center|thumb|alt=Spectrum|[[Media:198 PWR-RPV.txt]]]]<br />
<br />
==PWR-UO2-0==<br />
<br />
[[File:1102 PWR-UO2-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-0.txt]]]]<br />
<br />
==PWR-UO2-15==<br />
<br />
[[File:1102 PWR-UO2-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-15.txt]]]]<br />
<br />
==PWR-UO2-40==<br />
<br />
[[File:1102 PWR-UO2-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-40.txt]]]]<br />
<br />
==PWR-UO2-Gd-0==<br />
<br />
[[File:1102 PWR-UO2-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-0.txt]]]]<br />
<br />
==PWR-UO2-Gd-15==<br />
<br />
[[File:1102 PWR-UO2-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-15.txt]]]]<br />
<br />
==PWR-UO2-Gd-40==<br />
<br />
[[File:1102 PWR-UO2-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-40.txt]]]]<br />
<br />
==Superphenix==<br />
<br />
[[File:172 Superphenix.png|550px|center|thumb|alt=Spectrum|[[Media:172 Superphenix.txt]]]]<br />
<br />
==TUD-NG==<br />
<br />
[[File:175 TUD-NG.png|550px|center|thumb|alt=Spectrum|[[Media:175 TUD-NG.txt]]]]<br />
<br />
==WCCB-FW==<br />
<br />
[[File:616 WCCB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCCB-FW.txt]]]]<br />
<br />
==WCCB-VV==<br />
<br />
[[File:616 WCCB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCCB-VV.txt]]]]<br />
<br />
==WCLL-FW==<br />
<br />
[[File:616 WCLL-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCLL-FW.txt]]]]<br />
<br />
==WCLL-VV==<br />
<br />
[[File:616 WCLL-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCLL-VV.txt]]]]</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=Reference_input_spectra&diff=871Reference input spectra2017-03-10T14:07:26Z<p>Michael Fleming: </p>
<hr />
<div>__NOTOC__<br />
<br />
The collapsed cross-sections depend strongly on the nature of the projectile spectra, and so it is important to use the appropriate spectrum together with the appropriately-weighted cross-section data. With the advances of modern simulation software and high resolution spectra the user is reminded of the importance of the tails, low or high-energy ones, on the reaction rates.<br />
<br />
The majority of neutron-application spectra stem from light-water assemblies, mock-ups or reactors where the integral responses are strongly, if not solely, influenced by the energy ranges of the fission spectra and thermal maxwellian. Fusion spectra that have been obtained from magnetic confinement (MCF) or inertial confinement fusion (ICF) present typical D-D 2.5 MeV, or D-T 14 MeV peaks sometimes accompanied by a higher-energy tail, but also showing rather different slowing-down profiles. Accelerator-driven beam spectra are important in their role in nuclear data acquisition and materials research, but also for medical therapeutic and diagnostic applications.<br />
<br />
In essence the particle spectrum profile, through the collapsing process, emphasises the energy region of most importance for each application. Transferring data from one application or energy range to another should be done with great care as it can easily lead to misleading and inappropriate numerical results.<br />
<br />
Several incident particle spectra are provided in the table below, mostly including neutron incident spectra but with some charged particle spectra. '''Note''' that these are provided in the original energy group structures as generated by the code(s) that calculated them. These are often ''not'' the same energy group structures as those provided for e.g. the TENDL nuclear data libraries and require a flux conversion using [[Keyword:GRPCONVERT | '''GRPCONVERT''']]. Note that while the group conversion can easily be performed, this cannot add structure when moving to a refined group structure when moving to a more refined multi-group.<br />
<br />
Each of the spectra below is provided in the format of an arbitrary flux <tt>arb_flux</tt> file for reading in the '''GRPCONVERT''' module as well as a figure showing the spectrum in flux per unit lethargy using an arbitrary normalisation. For convenience, all of the <tt>arb_flux</tt> files are available in the table below.<br />
<br />
<br />
{| class="wikitable sortable" <br />
|+ Reference incident particle spectra<br />
! Name<br />
! Group<br />
! Particle<br />
! <tt>arb_flux</tt> file<br />
! Figure<br />
! Description<br />
|-<br />
| Bigten<br />
| 407<br />
| n<br />
| [[Media:407 Bigten.txt]]<br />
| [[Reference_input_spectra#Bigten | Bigten]]<br />
| <br />
|-<br />
| BWR-MOX-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-0.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-0 | BWR-MOX-Gd-0]]<br />
| <br />
|-<br />
| BWR-MOX-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-15.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-15 | BWR-MOX-Gd-15]]<br />
| <br />
|-<br />
| BWR-MOX-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-MOX-Gd-40.txt]]<br />
| [[Reference_input_spectra#BWR-MOX-Gd-40 | BWR-MOX-Gd-40]]<br />
| <br />
|-<br />
| BWR-RPV<br />
| 198<br />
| n<br />
| [[Media:198 BWR-RPV.txt]]<br />
| [[Reference_input_spectra#BWR-RPV | BWR-RPV]]<br />
| <br />
|-<br />
| BWR-UO2-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-0.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-0 | BWR-UO2-Gd-0]]<br />
| <br />
|-<br />
| BWR-UO2-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-15.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-15 | BWR-UO2-Gd-15]]<br />
| <br />
|-<br />
| BWR-UO2-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 BWR-UO2-Gd-40.txt]]<br />
| [[Reference_input_spectra#BWR-UO2-Gd-40 | BWR-UO2-Gd-40]]<br />
| <br />
|-<br />
| CERN-H4IRRAD<br />
| 288<br />
| n<br />
| [[Media:288 CERN-H4IRRAD.txt]]<br />
| [[Reference_input_spectra#CERN-H4IRRAD | CERN-H4IRRAD]]<br />
| <br />
|-<br />
| Cf252<br />
| 070<br />
| n<br />
| [[Media:070 Cf252.txt]]<br />
| [[Reference_input_spectra#Cf252 | Cf252]]<br />
| <br />
|-<br />
| DEMO-HCPB-BP<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-BP.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-BP | DEMO-HCPB-BP]]<br />
| <br />
|-<br />
| DEMO-HCPB-FW<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-FW.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-FW | DEMO-HCPB-FW]]<br />
| <br />
|-<br />
| DEMO-HCPB-VV<br />
| 616<br />
| n<br />
| [[Media:616 DEMO-HCPB-VV.txt]]<br />
| [[Reference_input_spectra#DEMO-HCPB-VV | DEMO-HCPB-VV]]<br />
| <br />
|-<br />
| EBR-2<br />
| 029<br />
| n<br />
| [[Media:029 EBR-2.txt]]<br />
| [[Reference_input_spectra#EBR-2 | EBR-2]]<br />
| <br />
|-<br />
| Frascati-NG<br />
| 175<br />
| n<br />
| [[Media:175 Frascati-NG.txt]]<br />
| [[Reference_input_spectra#Frascati-NG | Frascati-NG]]<br />
| <br />
|-<br />
| HCLL-FW<br />
| 616<br />
| n<br />
| [[Media:616 HCLL-FW.txt]]<br />
| [[Reference_input_spectra#HCLL-FW | HCLL-FW]]<br />
| <br />
|-<br />
| HCLL-VV<br />
| 616<br />
| n<br />
| [[Media:616 HCLL-VV.txt]]<br />
| [[Reference_input_spectra#HCLL-VV | HCLL-VV]]<br />
| <br />
|-<br />
| HCPB-FW<br />
| 616<br />
| n<br />
| [[Media:616 HCPB-FW.txt]]<br />
| [[Reference_input_spectra#HCPB-FW | HCPB-FW]]<br />
| <br />
|-<br />
| HCPB-VV<br />
| 616<br />
| n<br />
| [[Media:616 HCPB-VV.txt]]<br />
| [[Reference_input_spectra#HCPB-VV | HCPB-VV]]<br />
| <br />
|-<br />
| HFIR-highres<br />
| 238<br />
| n<br />
| [[Media:238 HFIR-highres.txt]]<br />
| [[Reference_input_spectra#HFIR-highres | HFIR-highres]]<br />
| <br />
|-<br />
| HFIR-lowres<br />
| 100<br />
| n<br />
| [[Media:100 HFIR-lowres.txt]]<br />
| [[Reference_input_spectra#HFIR-lowres | HFIR-lowres]]<br />
| <br />
|-<br />
| HFIR-VXF3-AD<br />
| 238<br />
| n<br />
| [[Media:238 HFIR-VXF3-AD.txt]]<br />
| [[Reference_input_spectra#HFIR-VXF3-AD | HFIR-VXF3-AD]]<br />
| <br />
|-<br />
| HFR-high<br />
| 616<br />
| n<br />
| [[Media:616 HFR-high.txt]]<br />
| [[Reference_input_spectra#HFR-high | HFR-high]]<br />
| <br />
|-<br />
| HFR-low<br />
| 616<br />
| n<br />
| [[Media:616 HFR-low.txt]]<br />
| [[Reference_input_spectra#HFR-low | HFR-low]]<br />
| <br />
|-<br />
| IFMIF-DLi<br />
| 211<br />
| n<br />
| [[Media:211 IFMIF-DLi.txt]]<br />
| [[Reference_input_spectra#IFMIF-DLi | IFMIF-DLi]]<br />
| <br />
|-<br />
| ITER-DD<br />
| 175<br />
| n<br />
| [[Media:175 ITER-DD.txt]]<br />
| [[Reference_input_spectra#ITER-DD | ITER-DD]]<br />
| <br />
|-<br />
| ITER-DT<br />
| 175<br />
| n<br />
| [[Media:175 ITER-DT.txt]]<br />
| [[Reference_input_spectra#ITER-DT | ITER-DT]]<br />
| <br />
|-<br />
| JAEA-FNS<br />
| 175<br />
| n<br />
| [[Media:175 JAEA-FNS.txt]]<br />
| [[Reference_input_spectra#JAEA-FNS | JAEA-FNS]]<br />
| <br />
|-<br />
| JET-FW<br />
| 100<br />
| n<br />
| [[Media:100 JET-FW.txt]]<br />
| [[Reference_input_spectra#JET-FW | JET-FW]]<br />
| <br />
|-<br />
| LMJ-g<br />
| 161<br />
| γ<br />
| [[Media:161 LMJ-g.txt]]<br />
| [[Reference_input_spectra#LMJ-g | LMJ-g]]<br />
| <br />
|-<br />
| Maxwellians<br />
| 709<br />
| n<br />
| [[Media:709 Maxwellian-1keV.txt | 1 keV]] [[Media:709 Maxwellian-5keV.txt | 5 keV]] [[Media:709 Maxwellian-10keV.txt | 10 keV]] [[Media:709 Maxwellian-30keV.txt | 30 keV]] [[Media:709 Maxwellian-80keV.txt | 80 keV]]<br />
| [[Reference_input_spectra#NIF-ignition | Maxwellians]]<br />
| <br />
|-<br />
| NIF-ignition<br />
| 150<br />
| n<br />
| [[Media:150 NIF-ignition.txt]]<br />
| [[Reference_input_spectra#NIF-ignition | NIF-ignition]]<br />
| <br />
|-<br />
| Paluel<br />
| 172<br />
| n<br />
| [[Media:172 Paluel.txt]]<br />
| [[Reference_input_spectra#Paluel | Paluel]]<br />
| <br />
|-<br />
| Phenix<br />
| 172<br />
| n<br />
| [[Media:172 Phenix.txt]]<br />
| [[Reference_input_spectra#Phenix | Phenix]]<br />
| <br />
|-<br />
| PWR-MOX-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-0.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-0 | PWR-MOX-0]]<br />
| <br />
|-<br />
| PWR-MOX-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-15.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-15 | PWR-MOX-15]]<br />
| <br />
|-<br />
| PWR-MOX-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-MOX-40.txt]]<br />
| [[Reference_input_spectra#PWR-MOX-40 | PWR-MOX-40]]<br />
| <br />
|-<br />
| PWR-RPV<br />
| 198<br />
| n<br />
| [[Media:198 PWR-RPV.txt]]<br />
| [[Reference_input_spectra#PWR-RPV | PWR-RPV]]<br />
| <br />
|-<br />
| PWR-UO2-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-0.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-0 | PWR-UO2-0]]<br />
| <br />
|-<br />
| PWR-UO2-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-15.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-15 | PWR-UO2-15]]<br />
| <br />
|-<br />
| PWR-UO2-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-40.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-40 | PWR-UO2-40]]<br />
| <br />
|-<br />
| PWR-UO2-Gd-0<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-0.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-0 | PWR-UO2-Gd-0]]<br />
| <br />
|-<br />
| PWR-UO2-Gd-15<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-15.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-15 | PWR-UO2-Gd-15]]<br />
| <br />
|-<br />
| PWR-UO2-Gd-40<br />
| 1102<br />
| n<br />
| [[Media:1102 PWR-UO2-Gd-40.txt]]<br />
| [[Reference_input_spectra#PWR-UO2-Gd-40 | PWR-UO2-Gd-40]]<br />
| <br />
|-<br />
| Superphenix<br />
| 172<br />
| n<br />
| [[Media:172 Superphenix.txt]]<br />
| [[Reference_input_spectra#Superphenix | Superphenix]]<br />
| <br />
|-<br />
| TUD-NG<br />
| 175<br />
| n<br />
| [[Media:175 TUD-NG.txt]]<br />
| [[Reference_input_spectra#TUD-NG | TUD-NG]]<br />
| <br />
|-<br />
| WCCB-FW<br />
| 616<br />
| n<br />
| [[Media:616 WCCB-FW.txt]]<br />
| [[Reference_input_spectra#WCCB-FW | WCCB-FW]]<br />
| <br />
|-<br />
| WCCB-VV<br />
| 616<br />
| n<br />
| [[Media:616 WCCB-VV.txt]]<br />
| [[Reference_input_spectra#WCCB-VV | WCCB-VV]]<br />
| <br />
|-<br />
| WCLL-FW<br />
| 616<br />
| n<br />
| [[Media:616 WCLL-FW.txt]]<br />
| [[Reference_input_spectra#WCLL-FW | WCLL-FW]]<br />
| <br />
|-<br />
| WCLL-VV<br />
| 616<br />
| n<br />
| [[Media:616 WCLL-VV.txt]]<br />
| [[Reference_input_spectra#WCLL-VV | WCLL-VV]]<br />
| <br />
|}<br />
<br />
<br />
==Bigten==<br />
<br />
[[File:407 Bigten.png|550px|center|thumb|alt=Spectrum|[[Media:407 Bigten.txt]]]]<br />
<br />
==BWR-MOX-Gd-0==<br />
<br />
[[File:1102 BWR-MOX-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-0.txt]]]]<br />
<br />
==BWR-MOX-Gd-15==<br />
<br />
[[File:1102 BWR-MOX-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-15.txt]]]]<br />
<br />
==BWR-MOX-Gd-40==<br />
<br />
[[File:1102 BWR-MOX-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-MOX-Gd-40.txt]]]]<br />
<br />
==BWR-RPV==<br />
<br />
[[File:198 BWR-RPV.png|550px|center|thumb|alt=Spectrum|[[Media:198 BWR-RPV.txt]]]]<br />
<br />
==BWR-UO2-Gd-0==<br />
<br />
[[File:1102 BWR-UO2-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-0.txt]]]]<br />
<br />
==BWR-UO2-Gd-15==<br />
<br />
[[File:1102 BWR-UO2-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-15.txt]]]]<br />
<br />
==BWR-UO2-Gd-40==<br />
<br />
[[File:1102 BWR-UO2-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 BWR-UO2-Gd-40.txt]]]]<br />
<br />
==CERN-H4IRRAD==<br />
<br />
[[File:288 CERN-H4IRRAD.png|550px|center|thumb|alt=Spectrum|[[Media:288 CERN-H4IRRAD.txt]]]]<br />
<br />
==Cf252==<br />
<br />
[[File:070 Cf252.png|550px|center|thumb|alt=Spectrum|[[Media:070 Cf252.txt]]]]<br />
<br />
==DEMO-HCPB-BP==<br />
<br />
[[File:616 DEMO-HCPB-BP.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-BP.txt]]]]<br />
<br />
==DEMO-HCPB-FW==<br />
<br />
[[File:616 DEMO-HCPB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-FW.txt]]]]<br />
<br />
==DEMO-HCPB-VV==<br />
<br />
[[File:616 DEMO-HCPB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 DEMO-HCPB-VV.txt]]]]<br />
<br />
==EBR-2==<br />
<br />
[[File:029 EBR-2.png|550px|center|thumb|alt=Spectrum|[[Media:029 EBR-2.txt]]]]<br />
<br />
==Frascati-NG==<br />
<br />
[[File:175 Frascati-NG.png|550px|center|thumb|alt=Spectrum|[[Media:175 Frascati-NG.txt]]]]<br />
<br />
==HCLL-FW==<br />
<br />
[[File:616 HCLL-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCLL-FW.txt]]]]<br />
<br />
==HCLL-VV==<br />
<br />
[[File:616 HCLL-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCLL-VV.txt]]]]<br />
<br />
==HCPB-FW==<br />
<br />
[[File:616 HCPB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCPB-FW.txt]]]]<br />
<br />
==HCPB-VV==<br />
<br />
[[File:616 HCPB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 HCPB-VV.txt]]]]<br />
<br />
==HFIR-highres==<br />
<br />
[[File:238 HFIR-highres.png|550px|center|thumb|alt=Spectrum|[[Media:238 HFIR-highres.txt]]]]<br />
<br />
==HFIR-lowres==<br />
<br />
[[File:100 HFIR-lowres.png|550px|center|thumb|alt=Spectrum|[[Media:100 HFIR-lowres.txt]]]]<br />
<br />
==HFIR-VXF3-AD==<br />
<br />
[[File:238 HFIR-VXF3-AD.png|550px|center|thumb|alt=Spectrum|[[Media:238 HFIR-VXF3-AD.txt]]]]<br />
<br />
==HFR-high==<br />
<br />
[[File:616 HFR-high.png|550px|center|thumb|alt=Spectrum|[[Media:616 HFR-high.txt]]]]<br />
<br />
==HFR-low==<br />
<br />
[[File:616 HFR-low.png|550px|center|thumb|alt=Spectrum|[[Media:616 HFR-low.txt]]]]<br />
<br />
==IFMIF-DLi==<br />
<br />
[[File:211 IFMIF-DLi.png|550px|center|thumb|alt=Spectrum|[[Media:211 IFMIF-DLi.txt]]]]<br />
<br />
==ITER-DD==<br />
<br />
[[File:175 ITER-DD.png|550px|center|thumb|alt=Spectrum|[[Media:175 ITER-DD.txt]]]]<br />
<br />
==ITER-DT==<br />
<br />
[[File:175 ITER-DT.png|550px|center|thumb|alt=Spectrum|[[Media:175 ITER-DT.txt]]]]<br />
<br />
==JAEA-FNS==<br />
<br />
[[File:175 JAEA-FNS.png|550px|center|thumb|alt=Spectrum|[[Media:175 JAEA-FNS.txt]]]]<br />
<br />
==JET-FW==<br />
<br />
[[File:100 JET-FW.png|550px|center|thumb|alt=Spectrum|[[Media:100 JET-FW.txt]]]]<br />
<br />
==LMJ-g==<br />
<br />
[[File:161 LMJ-g.png|550px|center|thumb|alt=Spectrum|[[Media:161 LMJ-g.txt]]]]<br />
<br />
==Maxwellians==<br />
<br />
[[File:709 Maxwellian.png|550px|center|thumb|alt=Spectrum|[[Media:709 Maxwellian-1keV.txt | 1 keV]] [[Media:709 Maxwellian-5keV.txt | 5 keV]] [[Media:709 Maxwellian-10keV.txt | 10 keV]] [[Media:709 Maxwellian-30keV.txt | 30 keV]] [[Media:709 Maxwellian-80keV.txt | 80 keV]]]]<br />
<br />
==NIF-ignition==<br />
<br />
[[File:150 NIF-ignition.png|550px|center|thumb|alt=Spectrum|[[Media:150 NIF-ignition.txt]]]]<br />
<br />
==Paluel==<br />
<br />
[[File:172 Paluel.png|550px|center|thumb|alt=Spectrum|[[Media:172 Paluel.txt]]]]<br />
<br />
==Phenix==<br />
<br />
[[File:172 Phenix.png|550px|center|thumb|alt=Spectrum|[[Media:172 Phenix.txt]]]]<br />
<br />
==PWR-MOX-0==<br />
<br />
[[File:1102 PWR-MOX-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-0.txt]]]]<br />
<br />
==PWR-MOX-15==<br />
<br />
[[File:1102 PWR-MOX-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-15.txt]]]]<br />
<br />
==PWR-MOX-40==<br />
<br />
[[File:1102 PWR-MOX-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-MOX-40.txt]]]]<br />
<br />
==PWR-RPV==<br />
<br />
[[File:198 PWR-RPV.png|550px|center|thumb|alt=Spectrum|[[Media:198 PWR-RPV.txt]]]]<br />
<br />
==PWR-UO2-0==<br />
<br />
[[File:1102 PWR-UO2-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-0.txt]]]]<br />
<br />
==PWR-UO2-15==<br />
<br />
[[File:1102 PWR-UO2-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-15.txt]]]]<br />
<br />
==PWR-UO2-40==<br />
<br />
[[File:1102 PWR-UO2-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-40.txt]]]]<br />
<br />
==PWR-UO2-Gd-0==<br />
<br />
[[File:1102 PWR-UO2-Gd-0.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-0.txt]]]]<br />
<br />
==PWR-UO2-Gd-15==<br />
<br />
[[File:1102 PWR-UO2-Gd-15.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-15.txt]]]]<br />
<br />
==PWR-UO2-Gd-40==<br />
<br />
[[File:1102 PWR-UO2-Gd-40.png|550px|center|thumb|alt=Spectrum|[[Media:1102 PWR-UO2-Gd-40.txt]]]]<br />
<br />
==Superphenix==<br />
<br />
[[File:172 Superphenix.png|550px|center|thumb|alt=Spectrum|[[Media:172 Superphenix.txt]]]]<br />
<br />
==TUD-NG==<br />
<br />
[[File:175 TUD-NG.png|550px|center|thumb|alt=Spectrum|[[Media:175 TUD-NG.txt]]]]<br />
<br />
==WCCB-FW==<br />
<br />
[[File:616 WCCB-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCCB-FW.txt]]]]<br />
<br />
==WCCB-VV==<br />
<br />
[[File:616 WCCB-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCCB-VV.txt]]]]<br />
<br />
==WCLL-FW==<br />
<br />
[[File:616 WCLL-FW.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCLL-FW.txt]]]]<br />
<br />
==WCLL-VV==<br />
<br />
[[File:616 WCLL-VV.png|550px|center|thumb|alt=Spectrum|[[Media:616 WCLL-VV.txt]]]]</div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=File:709_Maxwellian-80keV.txt&diff=870File:709 Maxwellian-80keV.txt2017-03-10T14:01:36Z<p>Michael Fleming: </p>
<hr />
<div></div>Michael Fleminghttp://fispact.ukaea.uk/wiki/index.php?title=File:709_Maxwellian-30keV.txt&diff=869File:709 Maxwellian-30keV.txt2017-03-10T14:01:30Z<p>Michael Fleming: </p>
<hr />
<div></div>Michael Fleming