A thermal-fluid assessment of a cooled-vessel concept for a VHTR

Nuclear Engineering and Design

Volumn 238, Issue 12, 2008, Pages 3360-3369

  Kim, Min Hwan ^a   Lim, Hong Sik ^a   Lee, Won Jae ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

BOUNDARY VALUE PROBLEMS; CODES (SYMBOLS); COMPUTATIONAL FLUID DYNAMICS; CONCEPTUAL DESIGN; COOLING; DYNAMICS; FLUID DYNAMICS; NUCLEAR REACTORS; THERMOANALYSIS;

AVERAGE VALUES; CFD CODES; COMPUTATIONAL FLUID DYNAMICS CODES; COOLING FLOWS; CORE FLOWS; FLOW DISTRIBUTIONS; FLUID ANALYSES; GAMMA SYSTEMS; INLET FLOWS; NORMAL OPERATIONS; POSTULATED ACCIDENTS; REACTOR VESSELS; SAFETY MARGINS; THERMAL ANALYSIS; VERY HIGH TEMPERATURE REACTORS; VESSEL COOLING;

TRANSIENT ANALYSIS;

EID: 55049090182     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2008.06.022     Document Type: Article

References (11)

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