Application of environmentally-corrected fatigue curves to nuclear power plant components

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

Volumn 323, Issue , 1996, Pages 141-149

  Ware, A G ^a   Morton, D K ^a   Nitzel, M E ^a  

^a Lockheed Martin Idaho Technology Company   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING SYSTEMS; CURVE FITTING; FATIGUE OF MATERIALS; NUCLEAR POWER PLANTS; PRESSURE; TESTING;

ENVIRONMENTALLY-CORRECTED FATIGUE CURVES; FATIGUE RESISTANCE; NUCLEAR POWER PLANT COMPONENTS;

LIGHT WATER REACTORS;

EID: 0030372286     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (8)

1. American Society of Mechanical Engineers, 1992, "Boiler & Pressure Vessel Code", Section III, Division 1, 1992 Edition.
2. American Society of Mechanical Engineers, 1969, "USA Standard Code for Pressure Piping, Nuclear Power Piping", USAS B31.7, 1969 Edition.
3. American Society of Mechanical Engineers, 1967, "USA Standard Code for Pressure Piping, Power Piping", USAS B31.1, 1967 Edition.
4. Deardorff, A. F., and J. K. Smith, 1994, Evaluations of Conservatisms and Environmental Effects in ASME Code Section III, Class 1 Fatigue Analysis, SAND-94-0187, UC-523, Sandia National Laboratories.
5. Majumdar, S., Chopra, O. K., and Shack, W. J., 1993, Interim Fatigue Design Curves for Carbon, Low-Alloy, and Austenitic Stainless Steels in LWR Environments, NUREG/CR-5999.
6. Nitzel, M. E., A. G. Ware, and D. K. Morton, 1996, Comparison of ASME Code NB-3200 and NB-3600 Results for Fatigue Analysis of B31.1 PWR Branch Nozzles, to be presented at the ASME Pressure Vessel and Piping Conference, Montreal, Canada, July 21-26, 1996.
7. Sakai, T., et al., 1993, "Implementation of Automated, On-Line Fatigue Monitoring in a Boiling Water Reactor", ASME Pressure Vessel and Piping Conference, Denver, CO, July 25-29, 1993, PVP Volume 252, pp. 67-74.
8. Ware, A. G., D. K. Morton, and M. E. Nitzel, 1995, Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, NUREG/CR-6260, INEL-95-0045.