Fatigue life evaluation method of austenitic stainless steel in PWR water
Creators
- 1. Japan Nuclear Energy Safety Organization, JNES, TOKYUREIT Toranomon Building, 17-1, Toranomon 3-chome, Minato-ku, Tokyo 105-0001 (Japan)
- 2. Mitsubishi Heavy Industries, LTD, MHI, 16-5, Konan 2-chome, Minato-ku Tokyo, 1088215 (Japan)
- 3. IHI Corporation, TOYOSU IHI BUILDING, 1-1, Toyosu 3-chome, Koto-ku, Tokyo 135-8710 (Japan)
Description
It is known that the fatigue life in elevated temperature water is substantially reduced compared with that in the air. The fatigue life reduction has been investigated experimentally in EFT project of Japan Nuclear Energy Safety Organization (JNES) to evaluate the environmental effect on fatigue life. Many tests have been done for carbon, low alloy, stainless steels and nickel-based alloy under the various conditions. In this paper, the results of the stainless steel in simulated PWR water environments were reported. Fatigue life tests in simulated PWR environments were carried out and the effect of key parameters on fatigue life reduction was examined. The materials used in this study were base and weld metal of austenitic stainless steel SS316, weld metal of SS304 and the base and aged metal of the duplex stainless steel SCS14A. In order to evaluate the effects of stain amplitude, strain rate, strain ratio, temperature, aging, water flow rate and strain holding time, many fatigue tests were examined. In transient condition in an actual plant, however, such parameters as temperature and strain rate are not constant. In order to evaluate fatigue damage in actual plant on the basis of experimental results under constant temperature and strain rate condition, the modified rate approach method was developed. Various kinds of transient have to be taken into account of in actual plant fatigue evaluation, and stress cycle of several ranges of amplitude has to be considered in assessing damage from fatigue. Generally, cumulative usage factor is applied in this type of evaluation. In this study, in order to confirm the applicability of modified rate approach method together with cumulative usage factor, fatigue tests were carried out by combining stress cycle blocks of different strain amplitude levels, in which strain rate changes in response to temperature in a simulated PWR water environment. Consequently, fatigue life could be evaluated with an accuracy of factor of 3 by modified rate approach method. (authors)
Availability note (English)
Available from: SFEN, French Nuclear Energy Society, 5 rue des Morillons, F75015 Paris (France)Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- INIS-FR--08-0348
Conference
- Title
- Fontevraud 6. Contribution of materials investigations to improve the safety and performance of LWRs
- Original Conference Title
- Fontevraud 6. Contribution des expertises sur materiaux a l'amelioration de la surete et des performances des reacteurs a eau legere
- Dates
- 18-22 Sep 2006
- Place
- Fontevraud (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 39034063
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AUSTENITIC STEELS; EVALUATION; FATIGUE; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; SERVICE LIFE; STRAINS; TEMPERATURE DEPENDENCE; TESTING; WATER
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MECHANICAL PROPERTIES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 22 refs., 15 figs., 5 tabs.