Uncertainties in source term estimates for a station blackout accident in a BWR with Mark I containment
In this paper, attention is limited to a single accident progression sequence, namly a station blackout accident in a BWR with a Mark I containment building. Identified as an important accident in the draft version of NUREG-1150 a station blackout involves loss of both off-site power and dc power resulting in failure of the diesels to start and in the unavailability of the high pressure injection and core isolation cooling systems. This paper illustrates the calculated uncertainties (Probability Density Functions) associated with the radiological releases into the environment for the nine fission product groups at 10 hours following the initiation of core-concrete interactions. Also shown are the results ofthe STCP base case simulation. 5 refs., 1 fig., 1 tab.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5226329
- Report Number(s):
- BNL-NUREG-40751; CONF-880601-17; ON: DE88006373
- Resource Relation:
- Conference: American Nuclear Society annual meeting, San Diego, CA, USA, 12 Jun 1988
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
BLACKOUTS
SOURCE TERMS
FISSION PRODUCT RELEASE
MELTDOWN
MONTE CARLO METHOD
S CODES
ACCIDENTS
COMPUTER CODES
REACTOR ACCIDENTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
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