A state-of-the-art review of the reactor lower head models employed in three representative U.S. severe accident codes

Progress in Nuclear Energy

Volumn 42, Issue 3, 2003, Pages 361-382

  Ahn, Kwang Ii ^a   Kim, Dong Ha ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Critical Review; Lower Head Models; Melt Accident Progression; Modeling Uncertainties; Severe Accident Integral Codes

Indexed keywords

ACCIDENT PREVENTION; BOUNDARY CONDITIONS; CODES (STANDARDS); COMPUTER SIMULATION;

COMPUTER CODES;

NUCLEAR REACTORS;

EID: 0141953960     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0149-1970(03)90004-7     Document Type: Article

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