Use of probabilistic methods for estimating failure probabilities and directing ISI-efforts
Creators
- 1. Dept. of Technology, University of Uppsala, Box 534, S-75121 Uppsala (Sweden)
- 2. The Swedish Plant Inspectorate, Box 49306, 100 28 Stockholm (Sweden)
Description
Some general aspects of the role of NDT efforts on the resulting probability of core damage is discussed. A simple model for the estimation of the pipe break probability due to IGSCC is discussed. It is partly based on analytical procedures, partly on service experience from the Swedish BWR program. Estimates of the break probabilities indicate that further studies are urgently needed. It is found that the uncertainties about the initial crack configuration are large contributors to the total uncertainty. Some effects of the in-service inspection are studied and it is found that the detection probabilities influence the failure probabilities. Concluding remarks: - IGSCC seems to be the dominating contributor to pipe failure; - Probabilistic methods can be used to study the effects of ISI; - The need of exhaustive failure statistics is great. (authors)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Workshop on the Complementary roles of fracture mechanics and non-destructive examination in the safety assessment of components
- Imprint Pagination
- 538 p.
- Journal Page Range
- p. 97-102
- Report number
- NEA-CSNI-R--1991-14
Conference
- Title
- Workshop on the Complementary roles of fracture mechanics and non-destructive examination in the safety assessment of components
- Dates
- 3-5 Oct 1988
- Place
- Wuerenlingen (Switzerland)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39093669
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONFIGURATION; CRACKS; DAMAGE; DETECTION; FAILURES; IN-SERVICE INSPECTION; PROBABILISTIC ESTIMATION; PROBABILITY; STATISTICS
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; INSPECTION; MATHEMATICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- OCDE-GD--97-25