Overview of BWR Severe Accident Sequence Analyses at Oak Ridge National Laboratory
Description
Since its inception in October 1980, the Severe Accident Sequence Analysis (SASA) program at Oak Ridge National Laboratory (ORNL) has completed four studies including Station Blackout, Scram Discharge Volume Break, Loss of Decay Heat Removal, and Loss of Injection accident sequences for the Browns Ferry Nuclear Plant. The accident analyses incorporated in a SASA study provide much greater detail than that practically achievable in a Probabilistic Risk Assessment (PRA). When applied to the candidate dominant accident sequences identified by a PRA, the detailed SASA results determine if factors neglected by the PRA would have a significant effect on the order of dominant sequences. Ongoing SASA work at ORNL involves the analysis of Anticipated Transients Without Scram (ATWS) sequences for Browns Ferry
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84000645.Files
15021272.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- CONF-830816--42
Conference
- Title
- International meeting on light-water reactor severe accident evaluation.
- Dates
- 28 Aug - 1 Sep 1983.
- Place
- Cambridge, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15021272
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FAILURE MODE ANALYSIS; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ANALYSIS
- Descriptors DEC
- ACCIDENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS