Published 1997 | Version v1
Report

Use of probabilistic methods for estimating failure probabilities and directing ISI-efforts

  • 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)

Part of:
Proceedings of the Workshop on the Complementary roles of fracture mechanics and non-destructive examination in the safety assessment of components

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