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U.S. Department of Energy
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Environmentally assisted cracking in light water reactors

Technical Report ·
DOI:https://doi.org/10.2172/7261558· OSTI ID:7261558

This report summarizes work performed by Argonne National Laboratory on environmentally assisted cracking in light water reactors during the six months from April to September 1988. The stress corrosion cracking (SCC) of Types 316NG and 304 stainless steels (SSs) was investigated by means of slow-strain-rate and fracture-mechanics crack-growth-rate tests in high-temperature water. The effects of load ratio and water chemistry on the crack growth behavior of Type 316NG and sensitized Type 304 SS were determined in long-term fracture-mechanics tests. The influence of organic impurities on the SCC of sensitized Type 304 SS was also investigated. Fatigue tests were conducted on Type 316NG SS in air and simulated boiling water reactor water at 288{degrees}C to assess the degree of conservatism in the ASME Code Section III fatigue design curves. An ongoing investigation of the susceptibility of several heats of different grades of low-alloy ferritic steels to transgranular SCC in slow-strain-rate and fracture-mechanics tests was continued. 58 refs., 18 figs., 14 tabs.

Research Organization:
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Argonne National Lab., IL (USA)
Sponsoring Organization:
NRC
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
7261558
Report Number(s):
NUREG/CR-4667-Vol.7; ANL--89/40-Vol.7; ON: TI90008482
Country of Publication:
United States
Language:
English

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