The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis

Nuclear Engineering and Design

Volumn 186, Issue 1-2, 1998, Pages 23-37

  Wilson, Gary E ^a   Boyack, Brent E ^b  

^a IDAHO NATIONAL LABORATORY   (United States)

^b LOS ALAMOS NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; COMPUTER SOFTWARE SELECTION AND EVALUATION; COOLING; NUCLEAR REACTOR LICENSING; REACTOR CORES;

PHENOMENA IDENTIFICATION AND RANKING TABLE (PIRT) PROCESS; REACTOR SAFETY ANALYSIS;

LIGHT WATER REACTORS;

EID: 0032205848     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(98)00216-7     Document Type: Article

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