Development of MARS-GCR/V1 and its application to thermo-fluid safety analysis of gas-cooled reactors

Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05

Volumn 2, Issue , 2005, Pages 1189-1197

  Lee, Won Jae ^a   Jeong, Jae Jun ^a   Lee, Seung Wook ^a   Lee, Young Jin ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; CARBON DIOXIDE; HEAT TRANSFER; PROBLEM SOLVING;

CODE IMPROVEMENT; REACTOR CAVITY COOLING SYSTEM (RCCS); SAFETY ANALYSIS; THERMAL HYDRAULIC (TH) SAFETY ANALYSIS CODE;

GAS COOLED REACTORS;

EID: 34248998114     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

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