Development of nuclear data processing code FRENDY version 2

Abstract

ABSTRACTNuclear data processing is important to connect evaluated nuclear data libraries and radiation transport codes. The nuclear data processing code FRENDY version 1 was released in 2019 to generate ACE formatted cross section files with simple input data. After we released FRENDY version 1, many functions were developed, e.g., neutron multi-group cross section generation, explicit consideration of the resonance interference effect among different nuclides in a material, adaptive setting of the background cross sections, consideration of the resonance upscattering, ACE file perturbation, statistical uncertainty quantification of probability table, and modification of ENDF-6 formatted file. FRENDY version 2 was released including these new functions. It generates GENDF and MATXS formatted neutron multi-group cross section files from an ACE formatted cross section file or an evaluated nuclear data file. This paper explains the features of the new functions implemented in FRENDY version 2 and the verification of the neutron multigroup cross section generation function of this code.KEYWORDS: FRENDYnuclear data processingevaluated nuclear data libraryneutron multigroup cross section generationACEGENDFMATXSDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. Figure 1. Difference in the neutron multi-group cross section generation between a conventional code and FRENDY.Display full sizeFigure 2. Cross section of U-238 from JENDL-4.0 with and without resonance upscattering (MT=102, XMAS 172g).Display full sizeFigure 3. Secondary photon spectrum of Fe-56 from JENDL-4.0 (MT=102, Ein=12.5-12.8 MeV, VITAMIN-J 42g).Display full sizeFigure 4. Secondary photon spectrum of Fe-56 from JENDL-4.0 (MT=22, Ein=12.5-12.8 MeV, VITAMIN-J 42g).Display full sizeFigure 5. Example of the interpolation of energy with a ratio of 1:2 in the two-dimensional interpolation procedure.Display full sizeFigure 6. Comparison of secondary photon spectra of Fe-56 from JENDL-4.0 in each division number (MT=22, Ein=12.5-12.8 MeV, VITAMIN-J 42g)Display full sizeFigure 7. Secondary photon spectrum of Fe-56, MT=22, Ein=12 and 13 MeV from JENDL-4.0.Display full sizeFigure 8. Comparison of neutron spectra at the distance of 60 cm from the center of a 1 m radius Fe-56 sphere (JENDL-4.0, VITAMIN-B6 199g).Display full sizeFigure 9. Comparison of secondary photon spectra at the distance of 60 cm from the center of a 1 m radius Fe-56 sphere (JENDL-4.0, VITAMIN-J 42g).Display full size