Insights on the sensitivity and uncertainty in the risk of core damage from a typical BWR-5 plant
Creators
Description
This paper presents some of the insights obtained from a study of the uncertainty and sensitivity in the core damage risk from the operation of a BWR-5 plant. The results of the efforts to evaluate some of the sensitivities in the plant design, the impacts of plant modifications, and the importance of uncertainties in the plant data have shown that the problems of manipulating large amounts of risk data in an accessible format are now tractable. Event tree models provide the framework for the BWR-5 risk evaluation. These models were structured to meet the following objectives: provide a macro-level risk model that could be used as the basis for estimating plant risk measure sensitivities and uncertainties, and that could be enhanced with more detailed risk data and models; provide a basis for deriving some initial insights on the system level effects that are apparent for the plant, and for the preliminary identification of the important risk contributors; and provide a structure for implementing the various methodologies used for sensitivity and uncertainty analysis to gain a better understanding of the comparative techniques. The sensitivity and uncertainty results of this study provide a unique perspective on the way in which risk parameters are affected by changes in plant design or operation, analytic assumptions, and limitations in the data base
Additional details
Publishing Information
- Imprint Title
- International topical meeting on probabilistic safety methods and applications: proceedings. Volume 3. Sessions 17-23 and indexes
- Journal Page Range
- p. 138.1-138.10.
- Report number
- EPRI-NP--3912-SR-Vol.3
Conference
- Title
- International ANS/ENS topical meeting on probabilistic safety methods and applications.
- Dates
- 24 Feb - 1 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023531
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; FAILURE MODE ANALYSIS; FAILURES; PROBABILITY; REACTOR CORE DISRUPTION; REACTOR SAFETY; RELIABILITY; RESEARCH PROGRAMS; RISK ASSESSMENT; SENSITIVITY ANALYSIS; STATISTICAL MODELS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; MATHEMATICAL MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS