Published 1983 | Version v1
Report Open

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.

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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