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.
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October 1980
Research Papers
Reactor Surveillance Test and Fracture Mechanics Evaluation of Irradiation Embrittlement in Reactor Pressure Vessel Steels
Hideaki Takahashi,
Hideaki Takahashi
Department of Engineering Science, Tohoku University, Sendai/980 Japan
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Kiyoshi Saito,
Kiyoshi Saito
Department of Engineering Science, Tohoku University, Sendai/980 Japan
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Tetsuo Shoji,
Tetsuo Shoji
Department of Engineering Science, Tohoku University, Sendai/980 Japan
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Kazuhiro Date,
Kazuhiro Date
Department of Engineering Science, Tohoku University, Sendai/980 Japan
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Masahiko Suzuki
Masahiko Suzuki
Department of Engineering Science, Tohoku University, Sendai/980 Japan
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Hideaki Takahashi
Department of Engineering Science, Tohoku University, Sendai/980 Japan
Kiyoshi Saito
Department of Engineering Science, Tohoku University, Sendai/980 Japan
Tetsuo Shoji
Department of Engineering Science, Tohoku University, Sendai/980 Japan
Kazuhiro Date
Department of Engineering Science, Tohoku University, Sendai/980 Japan
Masahiko Suzuki
Department of Engineering Science, Tohoku University, Sendai/980 Japan
J. Eng. Mater. Technol. Oct 1980, 102(4): 317-326 (10 pages)
Published Online: October 1, 1980
Article history
Received:
September 28, 1979
Online:
September 15, 2009
Citation
Takahashi, H., Saito, K., Shoji, T., Date, K., and Suzuki, M. (October 1, 1980). "Reactor Surveillance Test and Fracture Mechanics Evaluation of Irradiation Embrittlement in Reactor Pressure Vessel Steels." ASME. J. Eng. Mater. Technol. October 1980; 102(4): 317–326. https://doi.org/10.1115/1.3224818
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