Published 1991 | Version v1
Book Metadata-only

Failure analysis module for the probabilistic fracture mechanics code for PWR steam generator tube maintenance

Creators

  • 1. Electricite de France (EDF), 93 - Saint-Denis (France)

Description

Examples described in this paper using the failure module in the COMPROMIS code show the advantage of a probabilistic analysis in studying break risks on steam generator tubes. (J.P.N.)

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
Transactions of the 11th international conference on structural mechanics in reactor technology
Imprint Pagination
6297 p.
Journal Page Range
v. G2 p. 307-312.

Conference

Title
11. international conference on structural mechanics in reactor technology.
Dates
18-23 Aug 1991.
Place
Tokyo (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
23049171
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRACKS; FAILURES; FRACTURE MECHANICS; MAINTENANCE; NUMERICAL SOLUTION; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; SENSITIVITY; SIZE; STEAM GENERATORS; TUBES
Descriptors DEC
BOILERS; ENRICHED URANIUM REACTORS; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Distributed by Maruzen Co. Ltd. P.O. Box 5050, Tokyo Int'l, 100-31 Japan ISBN 4-89047-060-3 for 17 vols. bound in 15 (A through SD2).