Environmentally assisted cracking in light water reactors. Semiannual progress report, January 1996--June 1996 | Zendy

O.K. Chopra | Zendy; H.M. Chung | Zendy; E.E. Gruber | Zendy

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Environmentally assisted cracking in light water reactors. Semiannual progress report, January 1996--June 1996

Author(s) -

O.K. Chopra,

H.M. Chung,

E.E. Gruber

Publication year - 1997

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/481873

Subject(s) - stress corrosion cracking , materials science , boiling water reactor , austenitic stainless steel , light water reactor , cracking , piping , metallurgy , carbon steel , ultimate tensile strength , alloy , corrosion fatigue , boiling , pressurized water reactor , austenite , strain rate , corrosion , nuclear engineering , composite material , environmental science , microstructure , chemistry , organic chemistry , environmental engineering , engineering

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from January 1996 to June 1996. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Type 304 SS, and (c) EAC of Alloys 600 and 690. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during various portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated boiling water reactor (BWR) water at 288{degrees}C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from several heats of Alloys 600 and 690 in air and high-purity, low-DO water. 83 refs., 60 figs., 14 tabs

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