Application of safety analysis code SIMMER-IV to blockage accidents in FASTEF subcritical core

Vladimir Kriventsev,Andrei Rineiski,Werner Maschek

Annals of Nuclear Energy（2014）

引用 13|浏览4

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摘要

•Safety analysis SIMMER-IV code is applied to the transient simulations of FASTEF/MYRRHA.•Unprotected blockage accidents are analyzed.•The FASTEF core can survive blockages up to 75% of the nominal flowrate.•In case of 100% TIB, core melting does no propagate to the whole core.

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关键词

Fast reactor,Lead–Bismuth Eutectic,Safety analysis,Unprotected blockage

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