HEIR high-energy reaction data From the 4.0 version onward, FISPACT-II possesses the ability to splice high-energy reaction cross sections in ENDF6 MF10 format. A special-purpose library, the High-Energy INCL-based Residual (HEIR) library, has been specifically developed to provide the ability to extend the physics of lower-energy ENDF6 data up to GeV energies.
TENDL complete reaction data The technologically generated TENDL has been released annually since 2008, now with eight distributions in as many years. Considerable experience has been developed from this process, which has been integrated into a fully programmed system, incorporating changes within code to make it as robust and reproducible as possible. The decision to translate lessons learned into the system has resulted in a project which experiences the positive opposite of the ‘nuclear ratchet’, where continual improvement is made each year. TENDL produces the only truly general-purpose, multi-particle nuclear data libraries which include all targets and reaction channels. Now with 2809 target nuclides, 543 isomeric states (as targets) and all isomeric products included in RIPL-3 with half-lives above 100 ms, full variance-covaraicne and production data up to 200 MeV, TENDL has reached a unique position amongst nuclear data libraries.

GEFY fission yields Fission yield files are required by inventory codes to populate the various nuclides which are produced in fission processes. These yields are of course dependent upon the charge and mass of the target nuclide, for example U235 and Pu239 generate quite different yields. They are also highly dependent upon the energy of the incident particle for numerous reasons, including the multi-chance fission probabilities which are available at different energies depending on the target.

GEFY-5.2 fission yield for Pu239 at 7 MeV, including first and second chance fission events. The complete nuclide chart is shown with a mass distribution is given in the corner.
Covariance data The TENDL libraries and GEF-generated fission yields possess complete covariance data from input parameter variation. Whereas the fission yield covariance does not yet have an agreed format within the ENDF6 structure, this can be accomodated through direct Total-Monte-Carlo methods. FISPACT-II directly accesses the covariance data in LB=1, 5, 6 and 8, projecting the covariance energy grid onto the group-wise cross section data of whatever group structure. The resulting projected covariances can then be collapsed into reaction rate uncertainties for further uncertainty quantification and propagation. More details can be found in this publication.