Safety studies for the MYRRHA critical core with the SIMMER-III code
Annals of Nuclear Energy(2017)
摘要
•SIMMER-III code is applied to analyze the MYRRHA critical core.•UTOP accident shows a slight prompt supercriticality.•The unprotected blockage accident leads to clad melting but without core damage propagation.•The protected core blockage results exclude the risks of possible recriticalities.•The investigation of possible damage propagation shows no risk of propagation.
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关键词
Reactor safety study,LBE cooled reactor,MYRRHA,SIMMER-III code,2-D simulations,Severe core disruptive accidents
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