A conservative analysis methodology for a steam-line-break accident of the SMART-P plant

Nuclear Technology

Volumn 153, Issue 1, 2006, Pages 41-52

  Chung, Young Jong ^a   Kim, Hee Kyung ^a   Kim, Hee Cheol ^a   Zee, Sung Quun ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Integral reactor; SMART P; Steam line break accident

Indexed keywords

ACCIDENT PREVENTION; CONTROL RODS; FLOW OF FLUIDS; NUCLEAR FUELS; NUCLEAR REACTOR ACCIDENTS; PRESSURE EFFECTS; REACTIVITY (NUCLEAR); REACTOR CORES; STEAM PIPING SYSTEMS; THERMAL EFFECTS;

HIGH COOLANT TEMPERATURE; HIGH SYSTEM PRESSURE; INTEGRAL REACTOR; STEAM-LINE-BREAK ACCIDENT; SYSTEM-INTEGRATED MODULAR ADVANCED REACTOR (SMART); THERMAL DESIGN FLOW;

NUCLEAR POWER PLANTS;

EID: 30844431714     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT06-A3688     Document Type: Review

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