Integral Experiment Analyses in support to the OECD/NEA benchmarks on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)
Résumé
Sodium fast reactors can answer three major challenges:
-Using the whole uranium ore ($^{238}$U and not only $^{235}$U),
-Burning radioactive waste (Plutonium or minor actinides) in order to reduce the size of the ultimate storage,
- An enhanced safety.
Designing reactors with improved safety performance while preserving a sustainable source of energy at an economically competitive cost requires to improve the performance of the modelling tools. It is the purpose of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM). Two SFR cores are being studied a large 3600 MWth oxide core and a medium 1000 MWth metallic core. For a reliable prediction of the characteristics of the core whose benchmark results are quite spread [3], it is necessary to use validated integral experiments of great confidence. It is the aim of the last task of the SFR-UAM task force to which this paper is contributing. Some OECD experimental benchmarks (available from the ICSBEP and in the IRPhE experimental data bases) have been identified as relevant to the SFR-UAM core characteristics, with the use of sensitivities. These experiments have been analysed here with JEFF3.1.1 and provide a base.
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