Published 1989 | Version v1
Book

Probabilistic integrity assessment of reactor pressure circuits

  • 1. Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.

Description

The authors discuss how probabilistic structural assessment methods can provide benefits for both the safe and economic performance of nuclear plant. Three areas of potential application are identified and discussed: as part of an overall plant safety analysis to substantiate a case for new plant or continued operation of old plant, as a guide to decisions on plant design or modification, and as a guide to economic deployment of resources on maintenance, inspection and repair. The main technical problems with probabilistic structural assessment techniques are the need for a knowledge of variability in loads, material properties, defect occurrence etc. and fast, efficient and flexible codes that can handle a variety of problems. The illustration described in this paper uses the specific example of components in a Magnox reactor top duct but the overall project was mainly concerned with the development of probabilistic methods that could be widely used in the CEGB. The two classes of components considered are straight duct sections and fabricated welded 90 degrees corner units (mitre bends). Both have an internal diameter of 2 m and wall thicknesses of between 28 and 50 mm

Additional details

Publishing Information

Publisher
American Association for Structural Mechanics in Reactor Technology.
Imprint Place
Los Angeles, CA (USA)
ISBN
0-9623306-0-4
Imprint Title
Transactions of the 10th international conference on structural mechanics in reactor technology
Imprint Pagination
223 p.
Series
Structural reliability.
Journal Page Range
p. 133-138.

Conference

Title
10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
Dates
14-18 Aug 1989.
Place
Anaheim, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21079913
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DYNAMIC LOADS; IN-SERVICE INSPECTION; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; REACTOR VESSELS; RISK ASSESSMENT; SPECIFICATIONS
Descriptors DEC
CONTAINERS; INSPECTION; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-890855--.