Published August 1990
| Version v1
Journal article
BWRSAR calculations of reactor vessel debris pours for Peach Bottom short-term station blackout
Creators
- 1. Oak Ridge National Lab., TN (USA). Boiling Water Reactor Severe Accident Technology (BWRSAT) Program
Description
This paper describes recent analyses performed by the BWR Severe Accident Technology (BWRSAT) Program at ORNL estimate the release of debris from the reactor vessel for the unmitigated short-term station blackout accident sequence. Calculations were performed with the BWR Severe Accident Response (BWRSAR) code and are based upon consideration of the Peach Bottom Atomic Power Station. The modeling strategies employed within BWRSAR for debris relocation within the reactor vessel are briefly discussed and the calculated events of the accident sequence, including details of the calculated debris pours, are presented. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 121
- Journal Issue
- 3
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 327-339
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- 16. water reactor safety information meeting (WRSM-16).
- Dates
- 24-28 Oct 1988.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 22009760
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CALCULATIONS; CONTAINMENT; CORIUM; MELTDOWN; OUTAGES; PEACH BOTTOM-1 REACTOR; REACTOR CORES; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DOE 1886-8045-2B; DE-AC05-84OR21400