Published 1989 | Version v1
Book

Development of a leak-before-break procedure for pressurized components

  • 1. CEGB, Berkeley Nuclear Lab., Berkeley (UK)

Description

For pressurized components there is an increasing interest in the use of leak-before-break arguments to show that defects will behave in a failsafe manner by growing in such a way as to cause a detectable leak before a disruptive failure of the pressure boundary can occur. The authors' company operates a wide variety of plant and has recognized the need for a flexible leak-before-break procedure which can be applied in a variety of different situations rather than the more rigid code approach adopted for LWR piping for example in NUREG-1061. This paper describes the development of such a procedure and discusses some of the key aspects of the leak-before-break procedure

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
375 p.
Series
Volume G. Fracture mechanics and non-destructive evaluation.
Journal Page Range
p. 287-292.

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
21068056
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; DYNAMIC LOADS; FAILURE MODE ANALYSIS; LEAK TESTING; N CODES; PRESSURE VESSELS; REACTOR COMPONENTS; REACTOR MONITORING SYSTEMS; REACTOR SAFETY; WATER COOLED REACTORS
Descriptors DEC
CONTAINERS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING

Optional Information

Secondary number(s)
CONF-890855--.