Difference between revisions of "FISPACT-II keywords"
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Revision as of 11:26, 8 September 2016
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 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.
| Keyword | Control | Initial | Invent. | Description |
|---|---|---|---|---|
| ATOMS | ✓ | ✓ | Sets initial conditions and initiates output with inventories and observables. After the ZERO keyword will also output uncertainties | |
| ATWO | ✓ | Causes output of legal limits for activity in transport of radioactive material | ||
| BREMSSTRAHLUNG | ✓ | Causes output of brehmsstrahlung contributions for specified nuclides | ||
| CLEAR | ✓ | Causes clearance data of radionuclides to be output | ||
| CLOBBER | ✓ | Allows FISPACT-II to overwrite existing output with same name | ||
| COVARIANCE | ✓ | Causes cross-channel covariances to be calculated (if present in nuclear data) | ||
| CULTAB | ✓ | Produces additional lines in tab files for specific post-processing tools | ||
| CUMFYLD | ✓ | Allows the cumulative fission yields to be read, rather than the default independent yields | ||
| DENSITY | ✓ | Specifies a density of the material in grams per cubic centimetre | ||
| DOSE | ✓ | Allows modification of the dose rate values from semi-infinite slab to point sources | ||
| END | ✓ | ✓ | Terminates the input of the simulation | |
| ENDPULSE | ✓ | Terminates the PULSE phase in the simulation | ||
| ERROR | ✓ | Allows manual override of error values for uncertainty quantification | ||
| FISCHOOSE | ✓ | Allows the user to select actinides for pathways-based uncertainty - note that this does not affect the use of fission in the inventory simulation | ||
| FISPACT | ✓ | A divider keyword which separates the library data preparation, initialising that process before subsequent actions | ||
| FISYIELD | ✓ | Allows the user to specify which fission yields are read and included in the inventory simulation | ||
| FLUX | ✓ | ✓ | Used to specify an incident particle flux in particles per square centimetre per second | |
| FUEL | ✓ | Specification of initial inventory by nuclide, rather than by element (which is done using MASS) | ||
| FULLXS | ✓ | ✓ | ✓ | Causes the full, energy-dependent group cross sections to be stored when the library is being collapsed |
| GENERIC | ✓ | Produces generic pathways data removing isomeric transitions | ||
| GETDECAY | ✓ | Causes the condense of decay data or reading of a pre-compiled binary file | ||
| GETXS | ✓ | ✓ | ✓ | Initiates the collapse of an incident particle spectrum with the cross sections to generate one-group values |
| GRAPH | ✓ | Causes the output of summarised graph files and plotting scripts in a variety of possible formats | ||
| GROUP | ✓ | Allows the specification of an output gamma group structure | ||
| GRPCONVERT | ✓ | ✓ | ✓ | Causes the conversion of an incident spectrum from one multi group to another |
| HALF | ✓ | Causes half-lives of all nuclides to be output at each step | ||
| HAZARDS | ✓ | Reads in ingestion/inhalation doses and outputs contributions from all nuclides at all steps | ||
| INDEXPATH | ✓ | Causes index of nuclides significant pathways to be written out | ||
| IRON | ✓ | Special keyword for low-impurity iron simulation, to remove iron responses and allow high-accuracy impurity analyses | ||
| LIBVERSION | ✓ | ✓ | ✓ | Controls input data format, allowing legacy EAF data to be used |
| LOGLEVEL | ✓ | ✓ | ✓ | Controls the sophistication of the logging outputs, particularly useful for error identification |
| LOOKAHEAD | ✓ | Fine-tunes pathway analyses by searching for long-lived nuclides and including them in post-irradiation dominant lists | ||
| MASS | ✓ | Input inventory specification by element, instead of by nuclide (as done with the FUEL keyword) | ||
| MCSAMPLE | ✓ | Used in conjunction with SENSITIVITY to change the Monte-Carlo sampling of nuclear data uncertainties | ||
| MCSEED | ✓ | Allows specification of random number seeds in Monte-Carlo sensitivity calculations | ||
| MIND | ✓ | Sets a minimum number of nuclides to follow in the simualation | ||
| MONITOR | ✓ | Controls whether or not FISPACT-II will output a description of the execution steps to the terminal | ||
| NOCOMP | ✓ | Causes the elemental composition table to be omitted from the output | ||
| NOERROR | ✓ | Turns off uncertainty from nuclear data files, although manual inclusion of error can be done using ERROR | ||
| NOFISS | ✓ | Stops the use of fission yield data from being processed and then used in the simulation | ||
| NOSORT | ✓ | Removes the output of dominant nuclides and subsequent pathways/uncertainty data | ||
| NOSTABLE | ✓ | Removes stable nuclides from the output files | ||
| NOT1 | ✓ | ✓ | Switches off the output of TAB1 | |
| NOT2 | ✓ | ✓ | Switches off the output of TAB2 | |
| NOT3 | ✓ | ✓ | Switches off the output of TAB3 | |
| NOT4 | ✓ | ✓ | Switches off the output of TAB4 | |
| OVER | ✓ | ✓ | Allows the manual overriding of cross sections, half-lives and their errors | |
| PARTITION | ✓ | Allows the partitioning of the inventory by element, making multiple parallel simulations | ||
| PATH | ✓ | Specifies a specific pathway which will be included in the pathways analysis | ||
| PATHRESET | ✓ | ✓ | Initiates a new pathways search and uncertainty quantification at the post-irradiation step that it is called in | |
| POWER | ✓ | ✓ | Causes the incident particle flux to be renormalised to match a specified volumetric power, using full kerma values from the nuclear data | |
| PRINTLIB | ✓ | Causes the printing of a range of library data, check the keyword options for more guidance | ||
| PROBTABLE | ✓ | ✓ | ✓ | Specifies the method of application of self-shielding factors |
| PROJECTILE | ✓ | Selects the incident particle used in the simulations, for example neutron or one of the four other charged particles currently allowed | ||
| PULSE | ✓ | Initiates a set of repeated irradiation steps with given flux and duration, must be ended with ENDPULSE | ||
| READSF | ✓ | Causes the reading and use of spontaneous fission yield data | ||
| RESULT | ✓ | Outputs the total number of atoms tracked in pathways analyses for the specified nuclides | ||
| ROUTES | ✓ | A method for specifying a range of pathways between two nuclides for inclusion in the pathways analyses | ||
| SAVELINES | ✓ | Causes spectral lines from the decay data to be stored and can be further printed using the PRINTLIB 5 option | ||
| SENSITIVITY | ✓ | Causes sensitivity calculations to be performed over a specified set of nuclides and reactions | ||
| SORTDOMINANT | ✓ | Controls the number of nuclides to blue included in the dominant lists and used in uncertainty quantification | ||
| SPECTRUM | ✓ | ✓ | Alternative to ATOMS which suppresses the full inventory output and gives the gamma spectrum | |
| SPEK | ✓ | Causes calculation of an approximate gamma spectrum for nuclides which have no spectral data | ||
| SPLIT | ✓ | Allows the display of additional gamma and beta heat data in the final summary table | ||
| SSFCHOOSE | ✓ | ✓ | ✓ | Selects the set of nuclides for which self-shielding factors will be applied |
| SSFDILUTION | ✓ | ✓ | ✓ | Allows manual override of dilution values for self-shielding factor calculation in a group-by-group basis |
| SSFFUEL | ✓ | ✓ | ✓ | 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 SSFMASS) |
| SSFGEOMETRY | ✓ | ✓ | ✓ | Provides spatial self-shielding using the universal sigmoid curve for foils, wires, spheres and cylinders |
| SSFMASS | ✓ | ✓ | ✓ | 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 SSFFUEL) |
| STEP | ✓ | Performs the same function of ATOMS but suppresses the output data | ||
| TAB1 | ✓ | ✓ | Writes the inventory data (atoms and mass) to a two column TAB1 file for easy post-processing | |
| TAB2 | ✓ | ✓ | Writes the activity and dose rate from each nuclide to a two column TAB2 file for easy post-processing | |
| TAB3 | ✓ | ✓ | Writes the ingestion and inhalation dose from each nuclide to a two column TAB3 file for easy post-processing | |
| TAB4 | ✓ | ✓ | Writes a multi-group gamma spectrum to a TAB4 file | |
| TIME | ✓ | ✓ | Sets the time-steps in the simulation and triggers the processing of any keyword actions that have been queued | |
| TOLERANCE | ✓ | Allows the modification of solver tolerance values | ||
| UNCERTAINTY | ✓ | Causes the code to perform pathways-based uncertainty quantification and allows manual control of algorithm parameters | ||
| UNCTYPE | ✓ | Allows the user to specify the uncertainties used in the simulation, including cross sections and/or half-lives | ||
| USEFISSION | ✓ | Causes fission yields to be included in the inventory matrix | ||
| WALL | ✓ | ✓ | Allows the input of a neutron first wall loading in surface power, which will renormalise the incident particle flux | |
| ZERO | ✓ | Resets the time and moves the simulation into the cooling phase, initiates pathways analyses, uncertainty calculations and output of GRAPH data |
