Comparison of Japanese MITI guideline and other methods for evaluation of environmental fatigue life reduction

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 419, Issue , 2000, Pages 73-81

  Iida, Kunihiro ^a   Higuchi, Makoto ^b   Bannai, Toshihiro ^c   Tsutsumi, Kazuya ^d   Sakaguchi, Katsumi ^e  

^a Japan Power Engineering and Inspection Corporation   (Japan)

^b IHI CORPORATION   (Japan)

^c Ministry of International Trade and Industry   (Japan)

^d MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

^e Japan Pwr Eng and Inspection Corp   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

LIGHT WATER REACTORS; STRAIN RATE; STRESS ANALYSIS; WELDING;

FATIGUE INITIATION;

FATIGUE OF MATERIALS;

EID: 0242455989     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Review

References (9)

1. Higuchi, M. and Iida, K., 1991, "Fatigue Strength Correction Factors for Carbon and Low-Alloy Steels in Oxygen-containing High-Temperature Water," Nuclear Engineering and Design, Vol. 129, pp. 293-306.
2. "MITI Guideline for Evaluating Fatigue Initiation Life Reduction in LWR Environment," (in Japanese), September, 2000.
3. Higuchi, M., Iida, K. and Asada, Y., 1995, "Effects of Strain Rate Change on Fatigue Life of Carbon Steel in High Temperature Water," ASME PVP Vol. 306, pp. 111-116.
4. en for carbon and Low Alloy Steels in LWR Water Environments," ASME PVP Vol. 410-2 ", pp. 35-44.
5. Tsutsumi, K., Kanasaki, H., Umakoshi, T., Nakamura, T., Urata, S., Mizuta, H. and Nomoto, S., 2000, "Fatigue Life Reduction in PWR Water Environment for Stainless Steels," ASME PVP Vol. 410-2, pp. 23-33.
6. Mujumdar, S., Chopra, O. and Shack, W., 1993, "Interim Fatigue Design Curves for Carbon, Low-Alloy, and Austenitic Stainless Steels in LWR Environments", NUREG/CR-5999, ANL-93/3.
7. Chopra, O., 2000, "Environmental Effects on Fatigue Crack Initiation in Piping and Pressure Vessel Steels," International Conference on Fatigue of Reactor Components, July 31 - August 2, 2000, Napa, California, USA.
8. Mehta, H. and Gosselin, S., 1995, "An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel and Piping Fatigue Evaluation", EPRI TR-105759, Work Order 3321-03, Final Report, 1995
9. Mehta, H., 2000, "An Update on The Consideration of Reactor Water Effects in Code Fatigue Initiation Evaluations for Pressure Vessels and Piping," ASME PVP-Vol. 410-2, pp. 45-51.