Published May 2001 | Version v1
Miscellaneous

A probabilistic prediction of primary water stress corrosion cracking in CRDM nozzles

  • 1. Seoul National Univ., Seoul (Korea, Republic of)

Description

Since a vessel head penetration had been found leaking at French Bugey 3 plant is 1991, many researches have been performed upon the cracking by PWSCC in CRDM nozzle penetrations. The prediction of both initiation and propagation of nozzle cracks in CRDM must be one of most important issues in the viewpoint of maintenance, safety review and life extension of nuclear power plant. In this study, an improved probabilistic analysis method based on Weibull distribution normalized by key parameters is presented through both vessel inspection data of domestic and foreign nuclear power plants and experimental data of many laboratories, and the applicability to the prediction of crack initiation is evaluated using a specific plant operational condition. The probabilistic approach used in this study might be considered as a realistics method for the prediction of crack initiation in vessel head penetrations with variously different kinds of influencing parameters, though this approach could not make a physically accurate prediction of crack initiation

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[13 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33040494
Subject category
S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CRACK PROPAGATION; NOZZLES; NUCLEAR POWER PLANTS; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; REACTOR VESSELS; SAFETY ANALYSIS; STRESS CORROSION; WATER
Descriptors DEC
CHEMICAL REACTIONS; CONTAINERS; CORROSION; HYDROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
15 refs, 6 figs, 5 tabs