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TECHNICAL PAPERS

Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels

[+] Author and Article Information
S. Murakami, A. Miyazaki, M. Mizuno

Department of Mechanical Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan

J. Eng. Mater. Technol 122(1), 60-66 (Jul 09, 1999) (7 pages) doi:10.1115/1.482766 History: Received April 13, 1998; Revised July 09, 1999
Copyright © 2000 by ASME
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References

Figures

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Schematic stress-strain curves of unirradiated and irradiated materials
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RVE of unirradiated and irradiated materials at damage initiation
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True stress-true strain curves of unirradiated and irradiated A533B cl. 1 steel at 260°C
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Damage of unirradiated and irradiated A533B cl. 1 steel at 260°C
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Predicted and experimental yield stress of unirradiated and irradiated A533B cl. 1 steel at 260°C 111213
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Predicted and experimental ultimate tensile strength of unirradiated and irradiated A533B cl. 1 steel at 260°C 1113
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Predicted and experimental total elongation of unirradiated and irradiated A533B cl. 1 steel at 260°C 1113
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Predicted and experimental strain hardening of unirradiated and irradiated A533B cl. 1 steel at 260°C 1113
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Predicted and experimental strain rate dependence of yield stress of unirradiated and irradiated A533B cl. 1 steel at 260°C 13

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