Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments
- Argonne National Lab., IL (United States)
Existing data in the literature on fatigue of carbon, low-alloy, and austenitic stainless steels in LWR environments are reviewed. It is found that both temperature and dissolved-oxygen concentration in water significantly affect fatigue life. At the very low dissolved-oxygen levels characteristic of pressurized water reactors and boiling water reactors with hydrogen-water chemistry. environmental effects on fatigue life are modest. However, at higher dissolved-oxygen levels ({ge}100 ppB), significant reductions in fatigue life can occur. The susceptibility of carbon and low-alloy steels to reduced fatigue life is strongly related to sulfur concentration. Although the fatigue lives of austenitic stainless steels may be reduced, the reductions are much smaller than those observed in high-sulfur carbon and low-alloy steels. In oxygenated water, fatigue life depends strongly on strain rate. Interim fatigue design curves are proposed that take Into account temperature, dissolved-oxygen level in the water, the sulfur level in the steel, and strain rate. Design curves for carbon and low-alloy steels for lives up to 10{sup 8} cycles are also proposed.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Argonne National Lab., IL (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10149694
- Report Number(s):
- NUREG/CR-5999; ANL-93/3; ON: TI93012532
- Resource Relation:
- Other Information: PBD: Apr 1993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
BWR TYPE REACTORS
REACTOR COMPONENTS
PWR TYPE REACTORS
AUSTENITIC STEELS
FATIGUE
STAINLESS STEELS
CARBON STEELS
SULFUR ADDITIONS
CORROSION
FRACTURE MECHANICS
DISSOLVED GASES
STEEL-ASTM-A106
STEEL-ASTM-A533-B
ALLOYS
210100
210200
360103
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MECHANICAL PROPERTIES