Development of Molten Core Relocation Analysis Module MCRA in the Severe Accident Analysis Code SAMPSON

Journal of Nuclear Science and Technology

Volumn 37, Issue 3, 2000, Pages 225-236

  Satoh, Nobuhide ^a   Ujita, Hiroshi ^a   Miyagi, Kazumi ^b   Shirakawa, Noriyuki ^b   Horie, Hideki ^b   Nakahara, Katsuhiko ^b   Sasakawa, Hiroshi ^b  

^a Nuclear Power Engineering Corp   (Japan)

^b Nuclear Engineering Laboratory   (Japan)

Author keywords

Condensation; Crust formation; Experiment; Flow regime; Freezing; KROTOS; Mechanistic model; Melting; Nuclear reactor safety; Severe accident; Simulation codes; Vaporization

Indexed keywords

COMPUTER SIMULATION; COMPUTER SOFTWARE; CONDENSATION; FLUID DYNAMICS; FREEZING; MELTING; NITROGEN; NUCLEAR POWER PLANTS; NUCLEAR REACTOR ACCIDENTS; TWO PHASE FLOW; VAPORIZATION; WATER;

CRUST FORMATION; FLOW REGIME; MOLTEN CORE RELOCATION ANALYSIS MODULE; NITROGEN GAS BUBBLING; NUCLEAR REACTOR SAFETY; SEVERE ACCIDENT ANALYSIS;

NUCLEAR REACTORS;

EID: 0033742997     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2000.9714888     Document Type: Article

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