Safety analysis for an inadvertent control rod withdrawal event during a power operation of an advanced integral reactor

Nuclear Engineering and Design

Volumn 237, Issue 10, 2007, Pages 1060-1070

  Yang, Soo Hyung ^a   Chung, Young Jong ^a   Zee, Sung Quun ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; FEEDBACK; HEAT FLUX; NUCLEAR POWER PLANTS; REACTOR CORES; SAFETY FACTOR;

ADVANCED INTEGRAL REACTORS; CRITICAL HEAT FLUX RATIO (CHFR); MAIN COOLANT PUMP (MCP); SAFETY ANALYSIS;

CONTROL RODS;

EID: 34247107173     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2006.12.004     Document Type: Article

References (8)

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