This is kind of related to OpenMC. I’ve been looking at cross sections and have used the openmc_data repository to generate/merge cross section files. I have a question about trying to create a library for Spectra-PKA. I have a library supposedly derived from TENDL2025. I was wondering if I could use OpenMC or OpenMC-related tools to accomplish this. I tried looking up documentation on how to/what is included in terms of formatting, but I couldn’t find anything. This is a long shot, but does anyone have any experience with this? I’m looking to create my own spectra pka library because it is missing some nuclides. Thank you!
I have a custom experimental workflow to produce FISPACT nuclear data files. But not Spectra-PKA. It mostly works with njoy and prepro, and nothing direct from OpenMC.
SPECTRA-PKA uses NJOY-generated recoil cross section matrices. The output files required from NJOY are non-standard and are produced by a slightly modified version of the GROUPR module within NJOY. 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 — see the detailed listing of nuclear data for FISPACT-II (and SPECTRA-PKA) at [1]. These can be used immediately with SPECTRA-PKA, or can be used as a template to guide users who may want to create their own input data files (for example, for libraries not currently included on the download page).