Published September 2006 | Version v1
Report

Fatigue life evaluation method of austenitic stainless steel in PWR water

  • 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)

Optional Information

Notes
22 refs., 15 figs., 5 tabs.