Speaker
Description
The GALILÉE-1 code developed at CEA Saclay has now reached a level of maturity that enables it to produce application libraries for the Monte Carlo transport code TRIPOLI-4. The two recent libraries JEFF-4 and ENDF/B-VIII.1 are now fully processed by GALILÉE-1, whereas previously it was necessary to use NJOY and CALENDF.
New representations of thermal scattering laws (TSL), including the coexistence of coherent and incoherent elastic scattering, are also handled by GALILÉE-1. Processing of TSL data has undergone significant improvements in cross-section quality, with fluctuations now correctly calculated by GALILÉE-1 in agreement with FRENDY and GRUKON through the use of an adaptive energy mesh, replacing the fixed grid imposed in NJOY/THERMR. Resonant up-scattering has also been implemented in GALILÉE-1 with the aim of preparing multigroup libraries for deterministic codes.
Another major progress in the development of GALILÉE-1 is the support of the GNDS format for neutron–nucleus interaction evaluation files. Processing is equivalent for both formats, ENDF-6 and GNDS, and the cross sections reconstructed from resonance parameters are consistent.
The next major step in the development of GALILÉE-1 will focus on formatting secondary particle data produced in nuclear reactions. This step is important as it will enable the production of files in the ACE format, usable by many codes such as MCNP, OpenMC, SERPENT, and TRIPOLI-5. It is also a prerequisite for generating multigroup data for deterministic codes such as APOLLO-2 and APOLLO-3.
| Session | Processing and Benchmarking |
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