Application of EPRI/GE environmental factor approach to representative BWR pressure vessel and piping fatigue evaluations

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

Volumn 360, Issue , 1998, Pages 413-417

  Mehta, H S ^a  

^a GE ENERGY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

FATIGUE OF MATERIALS; NUCLEAR POWER PLANTS; PIPING SYSTEMS; PRESSURE VESSEL CODES; PRESSURE VESSELS; SERVICE LIFE;

ENVIRONMENTAL FATIGUE; FATIGUE CUMULATIVE USAGE FACTORS; REACTOR RECIRCULATION PIPING; REACTOR VESSEL FEEDWATER NOZZLE; REACTOR VESSEL SHELL;

BOILING WATER REACTORS;

EID: 0031630978     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Review

References (25)

1. Rules for Construction of Nuclear Power Plant Components," Section III, Division 1, 1992 ASME Boiler and Pressure Vessel Code, American Society of Mechanical Engineers.
2. NUREG/CR-4667, Environmentally Assisted Cracking in Light Water Reactors, Semiannual Reports: Volume 12 (August 1991), Volume 13 (March 1992), Volume 16 (September 1993) and Volume 17 (June 1994).
3. NUREG/CR-4667, Environmentally Assisted Cracking in Light Water Reactors, Semiannual Reports: Volume 12 (August 1991), Volume 13 (March 1992), Volume 16 (September 1993) and Volume 17 (June 1994).
4. NUREG/CR-4667, Environmentally Assisted Cracking in Light Water Reactors, Semiannual Reports: Volume 12 (August 1991), Volume 13 (March 1992), Volume 16 (September 1993) and Volume 17 (June 1994).
5. NUREG/CR-4667, Environmentally Assisted Cracking in Light Water Reactors, Semiannual Reports: Volume 12 (August 1991), Volume 13 (March 1992), Volume 16 (September 1993) and Volume 17 (June 1994).
6. Majumdar, S., Chopra, O.K. and Shack, W.J., "Interim Fatigue Design Curves for Carbon, Low-Alloy, and Austenitic Stainless Steels in LWR Environments," NUREG/CR-5999, April 1993.
7. Keisler, J., Chopra, O.K. and Shack, W.J., "Statistical Analysis of Fatigue Strain-Life Data for Carbon and Low-Alloy Steels," NUREG/CR-6237, August 1994.
8. Chopra, O.K. and Shack, W.J., "Effects of LWR Environments on Fatigue Life of Carbon and Low-Alloy Steels," ASME PVP-Volume 306 (1995).
9. Keisler, J., Chopra, O.K. and Shack, W.J., "Fatigue Strain-Life Behavior of Carbon and Low-Alloy Steels, Austenitic Stainless Steels, and Alloy 600 in LWR Environments," NUREG/CR-6335, August 1995.
10. Keisler, J.M., Chopra, O.K. and Shack, W.J., "Statistical Models for Estimating Fatigue Strain-life Behavior of Pressure Boundary Materials in Light Water Reactor Environments," Nuclear Engineering & Design, 167 (1996), pp. 129-154.
11. Chopra, O.K. and Shack, W.J., "Evaluation of Effects of LWR Coolant Environments on Fatigue Life of Carbon and Low-Alloy Steels," ASTM STP 1298 (1997).
12. Higuchi, M. and Iida, K., "Fatigue Strength Correction Factors for Carbon and Low-Alloy Steels in Oxygen-Containing High-Temperature Water," Nuclear Engineering and Design, 129 (1991) 293-306.
13. Higuchi, M., Iida, K. and Asada, Y., "Effects of Strain Rate Change on Fatigue Life of Carbon Steel in High-Temperature Water," ASME PVP-Volume 306 (1995).
14. Kanasaki, H., Hayashi, M., Iida, K. and Asada, Y., "Effects of Temperature Change on Fatigue Life of Carbon Steel in High-Temperature Water," ASME PVP-Volume 306 (1995).
15. Nakao, G., et al, "Effects of Temperature and Dissolved Oxygen Content on Fatigue Life of Carbon and Low Alloy Steels in LWR Water Environment," ASME PVP-Volume 306 (1995).
16. Kishida, K., Suzuki, S. and Asada, Y., "Evaluation of Environmental Fatigue Life for Light Water Reactor Components," ASME PVP-Volume 306 (1995).
17. Higuchi, M. and Iida, K., "Reduction in Low Cycle Fatigue Life of Austenitic Stainless Steels in High Temperature Water," ASME PVP-Volume 353 (1997).
18. Nakao, G., Higuchi, M., Kanasaki, H., Iida, K. and Asada, Y., "Effects of Temperature and Dissolved Oxygen Contents on Fatigue Lives of Carbon and Low Alloy Steels in LWR Water Environments," ASTM STP 1298 (1997).
19. Ware, A.G., Morton, D.K. and Nitzel, M.E., "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," NUREG/CR-6260, March 1995.
20. Mehta, H.S. and Gosselin, S.R., "An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure vessel and Piping Fatigue Evaluations," EPRI Report No. TR-105759, December 1995.
21. Mehta, H.S. and Gosselin, S.R., "An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure vessel and Piping Fatigue Evaluations," ASME PVP-Volume 323 (1996).
22. SECY-95-245, "Completion of Fatigue Action Plan," U.S. Nuclear Regulatory Commission, September 25, 1995.
23. Van Der Sluys, W.A. and Yukawa, S., "Status of PVRC Evaluation of LWR Coolant Environmental Effects on the S-N Fatigue Properties of Pressure Boundary Materials," ASME PVP-Volume 306 (1995).
24. Sakai, T., Tokunaga, K., Stevens, G.L., and Ranganath, S., "Implementation of Automated, On-line Fatigue Monitoring in a Boiling Water Reactor," ASME PVP Volume No. 252 (1993).
25. Hwang, H.L., Cole, J.R. and Bossi, D.M., "Fatigue Usage Factor Evaluation for an Integrally Reinforced Branch Connection using NB-3600 and NB-3200 Analysis Methods," ASME PVP Volume No. 313-2 (1995).