An overview of BWR Severe Accident Sequence Analyses at Oak Ridge National Laboratory: Chapter 10
Description
The purpose of the ORNL SASA analyses is to pre-determine the course of each of a series of severe accidents so as to establish the timing and the sequence of events; this information would be of use in the unlikely case that one of these accidents might actually occur. These studies also produce recommendations concerning the implementation of better system design and better emergency operating instructions and operator training to further decrease the probability of such an event. Four accident analyses including Station Blackout, Scram Discharge Volume (SDV) Break, Loss of Decay Heat Removal (DHR) and Loss of Injection Accident Sequences have been completed since the inception of the ORNL program in October 1980. Each study includes an accident sequence analysis to determine the probable sequence of events and a subsequent fission product transport analysis to determine the magnitude and timing of the associated releases from the boundaries of the secondary containment
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-89448-112-6
- Imprint Title
- Proceedings of the international meeting on light water severe accident evaluation
- Journal Page Range
- p. 5.1-5.2.
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
- 18014474
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONTAINMENT; EDUCATION; EMERGENCY PLANS; FAILURES; FISSION PRODUCT RELEASE; ORNL; OUTAGES; PROBABILITY; REACTOR ACCIDENTS; REACTOR OPERATORS; RECOMMENDATIONS; RESEARCH PROGRAMS; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; PERSONNEL; POWER REACTORS; REACTORS; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS