Effects of LWR environments on fatigue life of carbon and low-alloy steels

Technical Report · Wed Mar 01 00:00:00 EST 1995

DOI:https://doi.org/10.2172/108192· OSTI ID:108192

Chopra, O K; Shack, W J

SME Boiler and Pressure Vessel Code provides construction of nuclear power plant components. Figure I-90 Appendix I to Section III of the Code specifies fatigue design curves for structural materials. While effects of environments are not explicitly addressed by the design curves, test data suggest that the Code fatigue curves may not always be adequate in coolant environments. This paper reports the results of recent fatigue tests that examine the effects of steel type, strain rate, dissolved oxygen level, strain range, loading waveform, and surface morphology on the fatigue life of A 106-Gr B carbon steel and A533-Gr B low-alloy steel in water.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 108192
• Report Number(s): ANL/ET/CP-84133; CONF-950740-78; ON: TI95014084; TRN: 95:021874
• Resource Relation: Conference: Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995; Other Information: PBD: Mar 1995
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
STEEL-ASTM-A106
FATIGUE
FAILURES
PERFORMANCE TESTING
EXPERIMENTAL DATA
STEEL-ASTM-A533
WATER COOLED REACTORS
BOILERS
PRESSURE VESSELS
REACTOR COOLING SYSTEMS