Stress Corrosion Cracking Susceptibility of Low Alloy Steels Used for Reactor Pressure Vessel in High Temperature Oxygenated Water

[+] Author and Article Information
J. Kuniya, I. Masaoka, R. Sasaki

Hitachi Research Laboratory, Hitachi, Ltd., Hitachi-shi, Ibaraki-ken, Japan

H. Itoh

Hitachi Works, Hitachi, Ltd., Hitachi-shi, Ibaraki-ken, Japan

T. Okazaki

Kure Works, Babcock-Hitachi, Ltd., Kure-shi, Hiroshima-ken, Japan

J. Pressure Vessel Technol 107(4), 430-435 (Nov 01, 1985) (6 pages) doi:10.1115/1.3264477 History: Received November 28, 1984; Revised March 20, 1985; Online November 05, 2009


Studies have been done on stress corrosion cracking (SCC) susceptibility of low alloy steels in water containing dissolved oxygen. The fundamental factors which affect the SCC susceptibility were clarified, and the integrity of the reactor pressure vessel (RPV), in which these steels are used, was assessed from the standpoint of SCC initiation. The effects of applied stress, strain rate, dissolved oxygen concentration, and test temperatures, on the SCC susceptibility was examined utilizing uniaxial constant load tensile tests (UCL), and slow strain rate tests (SSRT).

Copyright © 1985 by ASME
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