Extension of ASTEC-Na capabilities for simulating reactivity effects in Sodium Cooled Fast Reactor

V. Matuzas,L. Ammirabile, L. Cloarec, D. Lemasson,S. Perez-Martin,A. Ponomarev

Annals of Nuclear Energy（2018）

引用 11|浏览8

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摘要

•ASTEC-Na Point Kinetics and reactivity feedback model is presented.•ASTEC-Na benchmarking of a ULOF transient against SAS-SFR code results is shown.•It has been verified that ASTEC-Na models are correctly implemented.•Differences are associated to material expansion and fuel thermo-mechanical models.

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关键词

JASMIN project,Sodium-cooled Fast Reactors,Neutronic reactivity feedback,Unprotected flow coast-down,Severe accidents

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