Environmentally assisted cracking in Light Water Reactors: Semiannual report, October 1994--March 1995. Volume 20 | Zendy

H.M. Chung | Zendy; O.K. Chopra | Zendy; D.J. Gavenda | Zendy; A.G. Hins | Zendy; T.F. Kassner | Zendy; W.E. Ruther | Zendy; W. J. Shack | Zendy; W.K. Soppet | Zendy

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Environmentally assisted cracking in Light Water Reactors: Semiannual report, October 1994--March 1995. Volume 20

Author(s) -

H.M. Chung,

O.K. Chopra,

D.J. Gavenda,

A.G. Hins,

T.F. Kassner,

W.E. Ruther,

W. J. Shack,

W.K. Soppet

Publication year - 1996

Publication title -

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

Language(s) - English

Resource type - Reports

DOI - 10.2172/205937

Subject(s) - stress corrosion cracking , materials science , metallurgy , alloy , ultimate tensile strength , boiling water reactor , scanning electron microscope , light water reactor , auger electron spectroscopy , strain rate , cracking , intergranular corrosion , austenitic stainless steel , corrosion , composite material , nuclear engineering , physics , nuclear physics , engineering

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRS) from October 1994 to March 1995. Topics that have been investigated include (a) fatigue of carbon and low-alloy steel used in reactor piping and pressure vessels, (b) EAC of Alloy 600 and 690, and (c) irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS. Fatigue tests were conducted on ferritic steels in water with several dissolvedoxygen (DO) concentrations to determine whether a slow strain rate applied during different portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Tensile properties and microstructures of several heats of Alloy 600 and 690 were characterized for correlation with EAC of the alloys in simulated LWR environments. Effects of DO and electrochemical potential on susceptibility to intergranular cracking of high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath irradiated in boiling water reactors were determined in slow-strain-rate-tensile tests at 289{degrees}C. Microchemical changes in the specimens were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements may contribute to IASCC of these materials

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