Applications of the RELAP5 code to the station blackout transients at the Browns Ferry Unit One Plant
As a part of the charter of the Severe Accident Sequence Analysis (SASA) Program, station blackout transients have been analyzed using a RELAP5 model of the Browns Ferry Unit 1 Plant. The task was conducted as a partial fulfillment of the needs of the US Nuclear Regulatory Commission in examining the Unresolved Safety Issue A-44: Station Blackout (1) the station blackout transients were examined (a) to define the equipment needed to maintain a well cooled core, (b) to determine when core uncovery would occur given equipment failure, and (c) to characterize the behavior of the vessel thermal-hydraulics during the station blackout transients (in part as the plant operator would see it). These items are discussed in the paper. Conclusions and observations specific to the station blackout are presented.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- OSTI ID:
- 6635154
- Report Number(s):
- EGG-M-11482; CONF-830103-25; ON: DE83006290
- Resource Relation:
- Conference: 2. international topical meeting on nuclear reactor thermal hydraulics, Santa Barbara, CA, USA, 11 Jan 1983
- Country of Publication:
- United States
- Language:
- English
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