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| Program name | Package id | Status | Status date |
|---|---|---|---|
| FIFRELIN-1.7 | NEA-1934/01 | Tested | 12-DEC-2024 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1934/01 | Linux-based PC | Gitlab |
The FIFRELIN code is a Monte Carlo implementation of the Becvar’s notion of Nuclear Realization extended to neutron/gamma/electron emission (similar to the statistical Hauser-Feshbach nuclear reaction theory) applied to the de-excitation of primary fission fragments. It provides the full kinematic information on the two final fission products of a binary fission as well as the emitted neutrons, photons and conversion electrons. Ascii files are provided along with an event tree containing the whole set of particle characteristics (useful for detector simulation). The input for FIFRELIN is the pre-neutron fission mass distributions and the average kinetic energy per mass. The RIPL-3 nuclear structure database is used at low excitation energy to construct the nuclear level schemes accounting for energy, spin, parity, half-life and branching ratio. These level schemes are completed by nuclear models at higher energy. This release treats spontaneous fission and neutron induced fission (before second chance fission). In addition, the FIFRELIN code can be used for de-exciting any kind of nucleus by neutron/gamma/electron emission, initial state E,J,pi being provided by the user.
It depends on the fissioning system and the accuracy required for a given observable. Pu242(sf): 100x500 cascades over 10 threads last 20 min on Intel® Xeon® Silver 4210R CPU @ 2.4 GHz. Statistical uncertainty for nubar 0.2% U235(nth,f): 500x2000 cascades over 30 threads last 5 h on Intel® Xeon® Silver 4210R CPU @ 2.4 GHz. Statistical uncertainty for nubar: 0.04%.
GEF code can be used in connection for producing primary fission fragment pre-neutron input data (mass yields, as well as charge yields and kinetic energy distributions. In addition, FIFRELIN can generate input file for PHITS/DCHAIN system code in order to calculate decay heat using fission product yields.
Keywords: benchmarks, cross-sections, evaluation, fission, nuclear data.
