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Title: Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments

Technical Report ·
OSTI ID:10149694
; ;  [1]
  1. 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