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Article Dans Une Revue Nuclear Engineering and Design Année : 2016

A physical tool for severe accident mitigation studies

Résumé

Within the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R&D program of CEA, the core behavior in case of severe accidents is being assessed. Such transients are usually simulated with mechanistic codes (such as SIMMER-III). As a complement to this code, which gives reference accidental transient, a physico-statistical approach is currently followed; its final objective being to derive the variability of the main results of interest for the safety. This approach involves a fast-running simulation of extended accident sequences coupling low-dimensional physical models to advanced statistical analysis techniques.
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Dates et versions

hal-03749439 , version 1 (11-08-2022)

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N. Marie, A. Bachrata, J.M. Seiler, F. Barjot, A. Marrel, et al.. A physical tool for severe accident mitigation studies. Nuclear Engineering and Design, 2016, 309, pp.224-235. ⟨10.1016/j.nucengdes.2016.08.042⟩. ⟨hal-03749439⟩
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