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2021 1

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computer code (CC) 1

design basis accidents (DBAs) 1

model 1

modeling 1

nuclear power plant (NPP) design 1

safety requirements 1

severe accidents (SAs) 1

system of codes for realistic analysis of severe accidents (SOCRAT) 1

water-cooled water-moderated (WWER) 1

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Experience gained in analyzing severe accidents for WWER RP using CC SOCRAT

Frontiers in Energy 2021, Volume 15, Issue 4,   Pages 872-886 doi: 10.1007/s11708-021-0796-2

Abstract: design basis accidents (DBAs) and beyond design basis accidents (BDBAs), including severe accidents (SAsFor a rigorous calculational justification of BDBAs and SAs, it is necessary to develop an integral CCrelocated into the reactor lower plenum (HEFEST)) was developed in Russia to analyze a wide range of SAsimportant for computational justification of the reactor plant (RP) safety at the in-vessel stage of SAsApproaches have been considered to develop calculational models and analyze SAs using CC SOCRAT.

Keywords： for realistic analysis of severe accidents (SOCRAT)     design basis accidents (DBAs)     severe accidents (SAs    

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Experience gained in analyzing severe accidents for WWER RP using CC SOCRAT

Journal Article