Published 1994
| Version v1
Book
Flaw tolerance as an alternative approach for operating plant fatigue evaluation
Creators
- 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--.