Flow and pressure-induced transient analysis of the supercritical-pressure, light-water-cooled and moderated reactor

Proceedings of the ASME/JSME International Conference on Nuclear Engineering, ICONE

Volumn 1, Issue Pt B, 1996, Pages 771-780

  Okano, Yasushi ^a   Koshizuka, Seiichi ^a   Oka, Yoshiaki ^a  

^a UNIVERSITY OF TOKYO   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; CODES (SYMBOLS); COMPUTER SIMULATION; COOLANTS; FEEDWATER HEATERS; FEEDWATER PUMPS; FLOW OF FLUIDS; HEAT FLUX; NUCLEAR FUEL CLADDING; PRESSURE EFFECTS; STAINLESS STEEL; URANIUM DIOXIDE;

DOUBLE TUBE WATER RODS; STAINLESS STEEL CLAD FUEL; SUPERCRITICAL PRESSURE LIGHT WATER COOLED AND MODERATED REACTOR; THERMAL NEUTRON SPECTRUM REACTOR;

LIGHT WATER REACTORS;

EID: 0030392974     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (10)