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U.S. Department of Energy
Office of Scientific and Technical Information

Environmentally assisted cracking in light water reactors

Technical Report ·
DOI:https://doi.org/10.2172/6819025· OSTI ID:6819025

This report summarizes work performed by Argonne National Laboratory on environmentally assisted cracking in light water reactors during the six months from October 1988 to March 1989. The effects of load ratio on stress corrosion cracking (SCC) of Types 316NG, 304, and CF-3M cast stainless steels (SSs) were investigated by fracture-mechanics crack-growth-rate (CGR) tests in high-temperature water. The influence of organic impurities on the SCC of Type 316NG SS was also investigated in long-term CGR tests. Tests to determine the susceptibility of 4-in.-diameter Types 316NG and 304 SS pipe weldments to SCC in simulated BWR environments have been conducted. The influence of carbonate at concentrations between 0.1 and 3300 ppM on the SCC behavior of sensitized Type 304 SS in deoxygenated water (<5 ppB) was determined in constant-extension-rate tensile tests. Fatigue tests were conducted on Type 316NG SS in air and BWR environments to assess the degree of conservatism in the ASME Code Section 3 fatigue design curves. CGR tests are being conducted to determine susceptibility of A533-Gr B low-alloy ferritic steel to SCC in simulated BWR environments. 39 refs., 20 figs., 7 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:
6819025
Report Number(s):
NUREG/CR-4667-Vol.8; ANL--90/4-Vol.8; ON: TI90012661
Country of Publication:
United States
Language:
English