Analysis of station blackout accidents for the Bellefonte pressurized water reactor
An analysis has been performed for the Bellefonte PWR Unit 1 to determine the containment loading and the radiological releases into the environment from a station blackout accident. A number of issues have been addressed in this analysis which include the effects of direct heating on containment loading, and the effects of fission product heating and natural convection on releases from the primary system. The results indicate that direct heating which involves more than about 50% of the core can fail the Bellefonte containment, but natural convection in the RCS may lead to overheating and failure of the primary system piping before core slump, thus, eliminating or mitigating direct heating. Releases from the primary system are significantly increased before vessel breach due to natural circulation and after vessel breach due to reevolution of retained fission products by fission product heating of RCS structures.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 7047133
- Report Number(s):
- NUREG/CR-4563; SAND-86-0576; ON: TI87003019
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BELLEFONTE-1 REACTOR
REACTOR ACCIDENTS
REACTOR OPERATION
BELLEFONTE-2 REACTOR
BLACKOUTS
EVALUATION
SYSTEMS ANALYSIS
ACCIDENTS
ENRICHED URANIUM REACTORS
OPERATION
POWER REACTORS
PWR TYPE REACTORS
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THERMAL REACTORS
WATER COOLED REACTORS
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220900* - Nuclear Reactor Technology- Reactor Safety
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Light-Water Moderated
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