BWR core thermal-hydraulic stability in anticipated transients without SCRAM
Creators
- 1. General Electric Co., San Jose, CA (USA)
- 2. Commonwealth Edison Co., Chicago, IL (USA)
Description
The potential exists for core thermal hydraulic density wave oscillations to occur in the boiling water reactor (BWR) during anticipated transients without scram (ATWS) events. Conditions which may lead to oscillations in ATWS result either from recirculation pump trip (RPT) from appropriate ATWS signals, or from the failure to scram during core oscillations. A program to evaluate these scenarios will assess the adequacy of the system design and emergency operating procedures relative to the reactor system performance. Evaluation of ATWS events with oscillations is extremely complex, and defining the bases for the analyses is critical to the success of the program. Accurate analysis requires detailed modeling of the sequence of events, the plant configuration, and initial conditions
Additional details
Publishing Information
- Imprint Title
- Proceedings of the International Workshop on Boiling Water Reactor Stability
- Imprint Pagination
- 548 p.
- Journal Page Range
- p. 433-445.
- Report number
- CSNI-R--178
Conference
- Title
- International Workshop on Boiling Water Reactor Stability.
- Dates
- 17-19 Oct 1990.
- Place
- Brookhaven, NY (USA).
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 22063741
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; BWR TYPE REACTORS; FLUID FLOW; OSCILLATIONS; REACTOR OPERATORS; REACTOR STABILITY; T CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DESIGN BASIS ACCIDENTS; ENRICHED URANIUM REACTORS; PERSONNEL; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; STABILITY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS