RELAP5 analyses of overcooling transients in a pressurized water reactor

Conference · Sat Jan 01 04:00:00 EST 1983

OSTI ID:5583171

Bolander, M A; Fletcher, C D; Ogden, D M; Stitt, B D; Waterman, M E

In support of the Pressurized Thermal Shock Integration Study sponsored by the United States Nuclear Regulatory Commission, the Idaho National Engineering Laboratory has performed analyses of overcooling transients using the RELAP5/MOD1.5 computer code. These analyses were performed for Oconee Plants 1 and 3, which are pressurized water reactors of Babcock and Wilcox lowered-loop design. Results of the RELAP5 analyses are presented, including a comparison with plant data. The capabilities and limitations of the RELAP5/MOD1.5 computer code in analyzing integral plant transients are examined. These analyses require detailed thermal-hydraulic and control system computer models.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5583171
• Report Number(s): EGG-M-12883; CONF-830901-10; ON: DE84000803
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
ENRICHED URANIUM REACTORS
OCONEE-1 REACTOR
OCONEE-3 REACTOR
POWER REACTORS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTORS
THERMAL SHOCK
WATER COOLED REACTORS
WATER MODERATED REACTORS