Evaluation of environmental fatigue life for light water reactor components
- 1. Ishikawajima-Harima Heavy Industries Co., Ltd., Yokohama (Japan)
- 2. Mitsubishi Heavy Industries Co., Ltd., Kobe (Japan). Kobe Shipyard and Machinery Works
- 3. Univ. of Tokyo (Japan). Dept. of Mechanical Engineering
Description
The existing fatigue design procedures for LWR components do not define the effects of the reactor coolant environment. Recent laboratory data suggested that environmental effects may invalidate the Code fatigue curves. This paper summarizes fatigue evaluation procedures and evaluation results of typical components in Japanese LWRs, taking environmental effects into consideration. Environmental fatigue correction factors have been developed by Higuchi and Iida as a function of strain rate, temperature and dissolved oxygen content, based on laboratory test data. However, these factors are applicable only under conditions where the environmental parameters are constant. In this paper, the factors were modified so as to be applied to conditions where the environmental parameters are variable as is the case with actual LWRs. This paper also presents calculations of fatigue usage for the BWR reactor pressure vessel nozzle and the PWR steam generator nozzle, using the modified correction factors in order to evaluate the environmental effects
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1337-1
- Imprint Title
- Fatigue and crack growth: Environmental effects, modeling studies, and design considerations. PVP-Volume 306
- Imprint Pagination
- 331 p.
- Journal Page Range
- p. 139-147.
Conference
- Title
- Joint ASME/JSME pressure vessels and piping conference.
- Dates
- 23-27 Jul 1995.
- Place
- Honolulu, HI (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27030938
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CARBON STEELS; COMPARATIVE EVALUATIONS; DATA; FATIGUE; LOW ALLOY STEELS; NOZZLES; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR COMPONENTS; SERVICE LIFE; STEAM GENERATORS; WATER COOLED REACTORS
- Descriptors DEC
- ALLOYS; BOILERS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; EVALUATION; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-950740--.