Model verification of the debris coolability analysis module in the severe accident analysis code ‘SAMPSON’

Journal of Nuclear Science and Technology

Volumn 38, Issue 4, 2001, Pages 229-241

  Ujita, Hiroshi ^a   Hidaka, Masataka ^b  

^a Nuclear Power Engineering Corp   (Japan)

^b HITACHI LTD   (Japan)

Author keywords

Core melt; Debris cooling; In vessel retention; Melting; Natural convection; Numerical simulation; Pressure vessels; Reactor safety; Severe accident; Solidification; Spreading; System analysis

Indexed keywords

CODES (STANDARDS); COMPUTER SIMULATION; COOLING; DEBRIS; MELTING; NATURAL CONVECTION; NUCLEAR POWER PLANTS; PRESSURE VESSELS; SOLIDIFICATION; SYSTEMS ANALYSIS; TEMPERATURE DISTRIBUTION;

DEBRIS COOLABILITY ANALYSIS (DCA);

NUCLEAR REACTORS;

EID: 0035302394     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2001.9715025     Document Type: Article

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