New results in the modeling of fission and radiative neutron capture with FIFRELIN

Litaize, O.*; Piau, V.*; Chalil, A.*; Ogawa, Tatsuhiko   ; Chebboubi, A.*; Gook, A.*; Gunsing, F.*; Kessedjian, G.*; Lhuillier, D.*; Mancusi, D.*; Materna, T.*; Oberstedt, A.*; Oberstedt, S.*; Serot, O.*; Thulliez, L.*

The Monte-Carlo code FIFRELIN was originally developed for the simulation of first chance fission of fissile nuclei. In this study, its interfaces to radiation transport code PHITS, extension for neutron capture reactions, and a function to calculate neutrinos from fission fragments were developed. In order to extend FIFRELIN for neutron capture reactions, accurate gamma-ray yield was obtained by tuning the level density considering the nuclide species and excitation energy. Accurate neutrino yield was obtained by adopting up-to-date database on the thermal neutron capture state. JAEA developed an interface of FIFRELIN to PHITS to perform new FIFRELIN benchmark using FIFRELIN-DCHAIN joint calculation.