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Thermal-hydraulic and core damage analysis of the station blackout transient in pressurized water reactors

Conference ·
OSTI ID:6315107
; ;
Analyses of a PWR station blackout transient performed by EG and G Idaho in support of the US Nuclear Regulatory Commission's Severe Accident Sequence Analysis (SASA) Program are presented. The RELAP5 and SCDAP computer codes were used to calculate the effects of concurrent loss of off-site power, on-site power, and emergency feedwater on the Babcock and Wilcox (B and W) designed Bellefonte PWR and the Westinghouse designed Seabrook PWR. Results provide insight into the timing of significant events, severity of core damage, and effect of differences between the two PWR designs on transient results.
Research Organization:
EG and G Idaho, Inc., Idaho Falls (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6315107
Report Number(s):
EGG-M-03584; CONF-840914-18; ON: DE85003426
Country of Publication:
United States
Language:
English

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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
BELLEFONTE-1 REACTOR
BLACKOUTS
COMPUTER CODES
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
R CODES
REACTORS
S CODES
SEABROOK-1 REACTOR
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS