Reactor Surveillance Test and Fracture Mechanics Evaluation of Irradiation Embrittlement in Reactor Pressure Vessel Steels

[+] Author and Article Information
Hideaki Takahashi, Kiyoshi Saito, Tetsuo Shoji, Kazuhiro Date, Masahiko Suzuki

Department of Engineering Science, Tohoku University, Sendai/980 Japan

J. Eng. Mater. Technol 102(4), 317-326 (Oct 01, 1980) (10 pages) doi:10.1115/1.3224818 History: Received September 28, 1979; Online September 15, 2009


With special reference to a nuclear reactor surveillance test, a new evaluation procedure for the fracture toughness from Charpy Vee-notch data is developed. This procedure utilizes a recrystallization-etch technique to determine the crack tip energy dissipation (Wp ) within an intense strain region or the dissipation rate (dWp /da). These two parameters serve to characterize the crack tip resistance to cleavage-controlled fracture initiation. The effects of specimen geometry, strain rate, temperature and notch acuity on the cleavage-controlled fracture toughness transition are explained using a critical value of Wp or dWp /da and a modified rate parameter. A feasibility of the new surveillance test procedure for evaluating the irradiation embrittlement of reactor pressure vessel steel, such as SA533B-1, is here verified experimentally, utilizing the Charpy or small compact tension specimen irradiated in a test reactor.

Copyright © 1980 by ASME
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