Published 1994 | Version v1
Book

Flaw tolerance as an alternative approach for operating plant fatigue evaluation

  • 1. Structural Integrity Associates, Inc., San Jose, CA (United States)

Description

In the design of Class 1 components for nuclear reactors, the ASME Boiler and Pressure Vessel Code requires that the suitability for cyclic operation be addressed to assure a fatigue-resistant design. During plant operation, the acceptability of the component may come in to question if new types of loading conditions are identified or if the number of plant cycles exceeds that considered in the original design. The most common approach for addressing this issue is by performing a revised fatigue evaluation, consistent with that considered in the original design. This paper presents an alternative approach for demonstrating acceptability for continued service using concepts from fracture mechanics

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1359-2
Imprint Title
Changing priorities of codes and standards: Failure, fatigue, and creep. PVP-Vol. 286
Imprint Pagination
181 p.
Journal Page Range
p. 61-65.

Conference

Title
1994 pressure vessels and piping conference.
Dates
19-23 Jun 1994.
Place
Minneapolis, MN (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26011162
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFECTS; EQUIPMENT; FATIGUE; IN-SERVICE INSPECTION; NUCLEAR POWER PLANTS; REACTOR COMPONENTS; REACTOR MATERIALS; RELIABILITY
Descriptors DEC
INSPECTION; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-940613--.