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RELAP5 thermal-hydraulic analyses of overcooling sequences in a pressurized water reactor

Conference ·
OSTI ID:6315102
; ; ; ; ; ;
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/MOD1.6 and MOD2.0 computer codes. These analyses were performed for the H.B. Robinson Unit 2 pressurized water reactor, which is a Westinghouse 3-loop design plant. Results of the RELAP5 analyses are presented. The capabilities of the RELAP5 computer code as a tool for analyzing integral plant transients requiring a detailed plant model, including complex trip logic and major control systems, are examined.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6315102
Report Number(s):
EGG-M-03684; CONF-840914-21; ON: DE85003425
Country of Publication:
United States
Language:
English

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