Use of RETRAN for determination of some BWR success criteria
- 1. The Cincinnati Gas and Electric Co., Cincinnati, OH
Description
The evaluation of the risks associated with severe accident and transient conditions of nuclear power plants by means of probabilistic risk assessment has increased significantly in the past few years. The determination of core melt frequency, for this evaluation, has previously been based on conservative assumptions of the system success criteria. System success criteria are the minimum available system configuration, operator actions, etc. required to safely shutdown a nuclear plant for a given accident or transient initiating event. This paper discusses the use of the RETRAN thermal-hydraulic system analysis code to determine bestestimate success criteria of the Wm. H. Zimmer plant for two operational transients with dominant risk potential. The risk implications resulting from the application of these realistic, best-estimate success criteria will also be examined
Additional details
Publishing Information
- Publisher
- Plenum Press.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Anticipated and abnormal plant transients in light water reactors, vol. 2
- Journal Page Range
- p. 995-1004.
Conference
- Title
- Anticipated and abnormal plant transients in light water reactors conference.
- Dates
- 26-29 Sep 1983.
- Place
- Jackson, WY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16068412
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; FORECASTING; HYDRAULICS; PROBABILITY; R CODES; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SHUTDOWN; RISK ASSESSMENT; THERMODYNAMICS; TRANSIENTS; ZIMMER-1 REACTOR; ZIMMER-2 REACTOR
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SHUTDOWN; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS