Large-scale reliability analysis by decomposition and integration
- 1. Japan Atomic Energy Research Institute
Description
In this decade, the risk analysis for light water reactor nuclear power plants and other related facilities has become of remarkable importance. However, the plants or facilities to be analyzed are, in most cases, large-scale and complicated. Fault tree analysis for such a large-scale and complicated system often requires extremely time- and cost-consuming works. In this paper, a new method for the reliability analysis of the large-scale and complicated system (large-scale reliability analysis, hereinafter) is presented. The method enables the large-scale reliability analysis to be carried out practically and efficiently by decomposing the system into several subsystems and integrating the results obtained through reliability analyses for subsystems. For the demonstration of the methodology, a reliability analysis for a safety-related system of BWR nuclear power plants is provided. The merits of the method are confirmed by this application and the validity is shown by comparing the result with that of Interim Reliability Evaluation Program
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. 152.1-152.10.
- 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
- 19023539
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; AVAILABILITY; BROWNS FERRY-1 REACTOR; BWR TYPE REACTORS; EFFICIENCY; FAILURES; FAULT TREE ANALYSIS; LOSS OF COOLANT; LOW PRESSURE COOLANT INJECTION; PROBABILITY; PWR TYPE REACTORS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SENSITIVITY ANALYSIS; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; ECCS; ENRICHED URANIUM REACTORS; MIXED SPECTRUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS