FISPACT-II uses a suite of nuclear data libraries, including:

- Groupwise cross section data [xs, with incident particles n,p,d,g,a,t,h]
- Radioactive decay data [decay]
- Fission yield data [fy (neutron-induced, spontaneous and non-neutron-induced)]
- Self-shielding probability tables [pts]

A range of different evaluations are available to download for each of these data types, corresponding to recent releases of libraries from around the world. For each group cross section library, multiple temperatures may be available. Typically, these include 293 K, 600 K and 900 K, with associated self-shielding probability tables. In addition, multiple energy group discretisations are available for a selection of libraries, including the CCFE 709 and 162 groups, UKAEA 1102 and CASMO 586. The different sublibraries available are listed in the table below with download links. In some cases, packaged versions area also available, which provide, for example, complete sets of cross section data for a given nuclear data library; but these downloads are large and a user is advised, instead, to select only those sublibraries needed for the application of interest. For more data, or data in another format, please contact the developers.

Library | Description | Download link |
---|---|---|

TENDL-2021 | 1102 group neutron-induced cross sections and probability tables at 294 K |
n-tendl21data.tar.bz2 |

TENDL-2021 | 162 group proton-induced cross sections | p-tendl2021.tar.bz2 |

TENDL-2021 | 162 group alpha-induced cross sections | a-tendl2021.tar.bz2 |

TENDL-2021 | 162 group deuteron-induced cross sections | d-tendl2021.tar.bz2 |

TENDL-2021 | 162 group gamma-induced cross sections | g-tendl2021.tar.bz2 |

decay_2020 | an updated general purpose decay data library | decay2020.tar.bz2 |

TENDL-2019 | 1102 group neutron-induced cross sections and probability tables at 294 K |
tendl19data.tar.bz2 |

TENDL-2019 | 709 group neutron-induced cross sections and probability tables at 294 K |
tendl19data709.tar.bz2 |

TENDL-2019 | 1102 group neutron-induced cross sections and probability tables at 600 K |
tendl19data600.tar.bz2 |

TENDL-2019 | 1102 group neutron-induced cross sections and probability tables at 900 K |
tendl19data900.tar.bz2 |

TENDL-2019 | 1102 group (p,d,g,a)-induced cross sections and neutron-induced probability tables at 294 K |
FISPACT-II-formatted files from the TENDL-2019 site |

CENDL-3.2 | 1102 group neutron-induced cross sections and probability tables at 294 K |
cendl32data.tar.bz2 |

ENDF/B-VIII.0 | full library: xs (n), nfy, sfy, decay, pts | ENDFB80data.tar.bz2 |

ENDF/B-VIII.0 | 709 group neutron-induced cross sections at 294 K | gxs-709.tar.bz2 |

ENDF/B-VIII.0 | Spontaneous fission yields | endfb80sfy.tar.bz2 |

ENDF/B-VIII.0 | Neutron-induced fission yields | endfb80nfy.tar.bz2 |

ENDF/B-VIII.0 | Radioactive decay data | decay.tar.bz2 |

TENDL-2017 | full library: xs (n,p,d,g,a,h,t), pts | TENDL2017data.tar.bz2 |

TENDL-2017 | 709 group probability tables for neutron-induced cross sections at 900 K | tp-709-900.tar.bz2 |

TENDL-2017 | 709 group probability tables for neutron-induced cross sections at 600 K | tp-709-600.tar.bz2 |

TENDL-2017 | 709 group probability tables for neutron-induced cross sections at 294 K | tp-709-294.tar.bz2 |

TENDL-2017 | 709 group neutron-induced cross sections at 294 K | gxs-709.tar.bz2 |

TENDL-2017 | 709 group neutron-induced cross sections at 900 K | gxs-709-900.tar.bz2 |

TENDL-2017 | 709 group neutron-induced cross sections at 600 K | gxs-709-600.tar.bz2 |

TENDL-2017 | 1102 group neutron-induced cross sections at 294 K | gxs-1102.tar.bz2 |

TENDL-2017 | 1102 group neutron-induced cross sections at 900 K | gxs-1102-900.tar.bz2 |

TENDL-2017 | 1102 group neutron-induced cross sections at 600 K | gxs-1102-600.tar.bz2 |

TENDL-2017 | 162 group triton-induced cross sections | gxs-162.tar.bz2 |

TENDL-2017 | 162 group proton-induced cross sections | gxs-162.tar.bz2 |

TENDL-2017 | 162group helion-induced cross sections | gxs-162.tar.bz2 |

TENDL-2017 | 162group gamma-induced cross sections | gxs-162.tar.bz2 |

TENDL-2017 | 162group deuteron-induced cross sections | gxs-162.tar.bz2 |

TENDL-2017 | 162group alpha-induced cross sections | gxs-162.tar.bz2 |

TENDL-2015 | full library: xs (n,p,d,g,a), pts | TENDL2015data.tar.bz2 |

TENDL-2015 | 162 group proton-induced cross sections | gxs-162.tar.bz2 |

TENDL-2015 | 709 group probability tables for neutron-induced cross sections at 900 K | tp-709-900.tar.bz2 |

TENDL-2015 | 709 group probability tables for neutron-induced cross sections at 600 K | tp-709-600.tar.bz2 |

TENDL-2015 | 709 group probability tables for neutron-induced cross sections at 294 K | tp-709-294.tar.bz2 |

TENDL-2015 | 1102 group probability tables for neutron-induced cross sections at 900 K | tp-1102-900.tar.bz2 |

TENDL-2015 | 1102 group probability tables for neutron-induced cross sections at 600 K | tp-1102-600.tar.bz2 |

TENDL-2015 | 1102 group probability tables for neutron-induced cross sections at 294 K | tp-1102-294.tar.bz2 |

TENDL-2015 | 709 group neutron-induced cross sections at 294 K | gxs-709.tar.bz2 |

TENDL-2015 | 709 group neutron-induced cross sections at 900 K | gxs-709-900.tar.bz2 |

TENDL-2015 | 709 group neutron-induced cross sections at 600 K | gxs-709-600.tar.bz2 |

TENDL-2015 | 709 group neutron-induced cross sections at kT=5 keV | gxs-709-5k.tar.bz2 |

TENDL-2015 | 709 group neutron-induced cross sections at kT=30 keV | gxs-709-30k.tar.bz2 |

TENDL-2015 | 1102 group neutron-induced cross sections at 294 K | gxs-1102.tar.bz2 |

TENDL-2015 | 1102 group neutron-induced cross sections at 900 K | gxs-1102-900.tar.bz2 |

TENDL-2015 | 1102 group neutron-induced cross sections at 600 K | gxs-1102-600.tar.bz2 |

TENDL-2015 | 162 group gamma-induced cross sections | gxs-162.tar.bz2 |

TENDL-2015 | 162 group deuteron-induced cross sections | gxs-162.tar.bz2 |

TENDL-2015 | 162 group alpha-induced cross sections | gxs-162.tar.bz2 |

TENDL-2014 | full library: xs (n,p,d,g,a), pts | TENDL2014data.tar.bz2 |

TENDL-2014 | 162 group proton-induced cross sections | gxs-162.tar.bz2 |

TENDL-2014 | 709 group probability tables for neutron-induced cross sections at 600 K | tp-709-600.tar.bz2 |

TENDL-2014 | 709 group probability tables for neutron-induced cross sections at 294 K | tp-709-294.tar.bz2 |

TENDL-2014 | 709 group neutron-induced cross sections at 294 K | gxs-709.tar.bz2 |

TENDL-2014 | 709 group neutron-induced cross sections at 600 K | gxs-709-600.tar.bz2 |

TENDL-2014 | 162 group gamma-induced cross sections | gxs-162.tar.bz2 |

TENDL-2014 | 162 group deuteron-induced cross sections | gxs-162.tar.bz2 |

TENDL-2014 | 162 group alpha-induced cross sections | gxs-162.tar.bz2 |

GEFY-6.1 | Spontaneous fission yields | gefy61_sfy.tar.bz2 |

GEFY-6.1 | Neutron-induced fission yields | gefy61_nfy.tar.bz2 |

GEFY-5.2 | Spontaneous fission yields | gef52_sfy.tar.bz2 |

GEFY-5.2 | Neutron-induced fission yields | gef52_nfy.tar.bz2 |

GEFY-4.2 | Spontaneous fission yields | gefy42_sfy.tar.bz2 |

GEFY-4.2 | Neutron-induced fission yields | gefy42_nfy.tar.bz2 |

ENDF/B-VII.1 | full library: xs (n), nfy, sfy, decay, pts | ENDFB71data.tar.bz2 |

ENDF/B-VII.1 | Radioactive decay data | decay.tar.bz2 |

ENDF/B-VII.1 | 586 group probability tables for neutron-induced cross sections at 600 K | tp-586-600.tar.bz2 |

ENDF/B-VII.1 | 586 group neutron-induced cross sections at 600 K | gxs-586-600.tar.bz2 |

ENDF/B-VII.1 | 709 group neutron-induced cross sections at 294 K | gxs-709.tar.bz2 |

ENDF/B-VII.1 | 709 group neutron-induced cross sections at 600 K | gxs-709-600.tar.bz2 |

ENDF/B-VII.1 | 709 group neutron-induced cross sections at 900 K | gxs-709-900.tar.bz2 |

ENDF/B-VII.1 | Spontaneous fission yields | endfb71sfy.tar.bz2 |

ENDF/B-VII.1 | Neutron-induced fission yields | endfb71nfy.tar.bz2 |

JENDL-4.0 | full library: xs (n,a), nfy, sfy, decay | JENDL4data.tar.bz2 |

JENDL-4.0 | Radioactive decay data | decay.tar.bz2 |

JENDL-4.0 | Radioactive decay data (Updated Decay Data File 2015) | ddf15.tar.bz2 |

JENDL-4.0 | Spontaneous fission yields | jendl4sfy.tar.bz2 |

JENDL-4.0 | Neutron-induced fission yields | jendl4nfy.tar.bz2 |

JENDL-4.0 | 709 group neutron-induced cross sections at 600 K | gxs-709.tar.bz2 |

JENDL-4.0 | 162 group alpha-induced cross sections | gxs-162.tar.bz2 |

JEFF-3.3 | full library: xs (n), nfy, sfy, decay, pts | JEFF33data.tar.bz2 |

JEFF-3.3 | 709 group probability tables for neutron-induced cross sections at 294 K | tp-709-294.tar.bz2 |

JEFF-3.3 | Spontaneous fission yields | jeff33sfy.tar.bz2 |

JEFF-3.3 | Neutron-induced fission yields | jeff33nfy.tar.bz2 |

JEFF-3.3 | 709 group neutron-induced cross sections at 294 K | gxs-709.tar.bz2 |

JEFF-3.3 | Radioactive decay data | decay.tar.bz2 |

JEFF-3.2 | full library: xs (n), nfy, sfy, decay | JEFF32data.tar.bz2 |

JEFF-3.2 | Radioactive decay data (JEFF-3.1.1) | decay.tar.bz2 |

JEFF-3.2 | Spontaneous fission yields (JEFF-3.1.1) | jeff311sfy.tar.bz2 |

JEFF-3.2 | Neutron-induced fission yields (JEFF-3.1.1) | jeff311nfy.tar.bz2 |

JEFF-3.2 | 709 group neutron-induced cross sections at 294 K | gxs-709.tar.bz2 |

EAF-2010 | full library: xs, nfy, decay | EAF2010data.tar.bz2 |

decay_2012 | general purpose decay data | decay.tar.bz2 |

HEIR-0.1 | 162 group high-energy proton-induced residual product cross sections | gxs-162.tar.bz2 |

HEAD-2009 | 162 group high-energy proton-induced residual product cross sections | gxs-sp-162.tar.bz2 |

HEAD-2009 | 709 group high-energy neutron-induced residual product cross sections | gxs-sp-709.tar.bz2 |

HEAD-2009 | 709 group high-energy neutron-induced residual product cross sections | gxs-sp-1102.tar.bz2 |

CENDL-3.1 | 709 group neutron-induced cross sections at 294 K | gxs-709.tar.bz2 |

UKFY-4.2 | Neutron-induced fission yields | UKFY42data.tar.bz2 |

UKFY-4.1 | fission yields: (p,d,a,g) | UKFY41data.tar.bz2 |

ebins | set of multi-group energy structures | ebins.tar.bz2 |

**Data download for SPECTRA-PKA**

SPECTRA-PKA is a command-line driven programme for calculating the expected primary knock-on atom (PKA) spectra for a given target nuclide under neutron or charged particle irradiation. See the wiki for more details. SPECTRA-PKA uses NJOY-generated recoil cross section matrices. An evolving selection of databases produced using various international reaction cross section libraries (for various incident particle types) have been pre-calculated and are available to download as compressed tar archives from:

Library | Sublibrary description | Download link |
---|---|---|

TENDL-2015 | neutron-induced PKA recoils matrices at 294 K | TENDL2015data-n-pka.tar.bz2 |

TENDL-2017 | neutron-induced PKA recoils matrices at 294 K | TENDL2017data-n-pka.tar.bz2 |

TENDL-2017 | alpha-induced PKA recoils matrices at 294 K | TENDL2017data-a-pka.tar.bz2 |

TENDL-2017 | proton-induced PKA recoils matrices at 294 K | TENDL2017data-p-pka.tar.bz2 |

TENDL-2017 | triton-induced PKA recoils matrices at 294 K | TENDL2017data-t-pka.tar.bz2 |

TENDL-2019 | neutron-induced PKA recoils matrices at 294 K | TENDL2019-n-pka.tar.bz2 |