Thermal hydraulic analysis for grid supported pressurized water reactor cores

Nuclear Engineering and Design

Volumn 239, Issue 8, 2009, Pages 1442-1460

  Shuffler, C ^a   Trant, J ^a   Malen, J ^a   Todreas, N ^a  

^a Massachusetts Institute of Technology Cambridge   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

1000 MW; COOLANT PUMPS; CORE DESIGN; CORE INTERNAL; DEPARTURE FROM NUCLEATE BOILING RATIOS; DESIGN LIMITS; FUEL BUNDLE; FUEL RODS; FUEL TEMPERATURE; FUEL TYPES; HYDRIDE FUEL; LARGE POWER; PITCH-TO-DIAMETER RATIOS; POWER DESIGN; POWER INCREASE; POWER OUT PUT; SQUARE ARRAY; THERMAL-HYDRAULIC ANALYSIS; THERMAL-HYDRAULIC PERFORMANCE;

COOLANTS; DESIGN; DROPS; EVAPORATIVE COOLING SYSTEMS; FUELS; HYDRAULICS; NUCLEATE BOILING; PRESSURE DROP; PRESSURIZED WATER REACTORS; REACTOR CORES; SMALL NUCLEAR REACTORS; WATER ANALYSIS; ZIRCONIUM ALLOYS;

LOSS OF COOLANT ACCIDENTS;

EID: 67349145364     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2008.12.028     Document Type: Article

References (10)

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