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NTIS 바로가기Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.40 no.3, 2008년, pp.225 - 232
Jang, Hun (Department of Nuclear and Quantum Engineering Korea Advanced Institute of Science and Technology) , Cho, Hyun-Chul (Department of Nuclear and Quantum Engineering Korea Advanced Institute of Science and Technology) , Jang, Chang-Heui (Department of Nuclear and Quantum Engineering Korea Advanced Institute of Science and Technology) , Kim, Tae-Soon (Nuclear Engineering and Technology Institute Korea Hydro and Nuclear Power Co., Ltd.) , Moon, Chan-Kook (Nuclear Engineering and Technology Institute Korea Hydro and Nuclear Power Co., Ltd.)
To understand the effect of the cyclic strain rate on the environmentally assisted cracking behaviors of SA508 Gr.1a low alloy steel in deoxygenated water at
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H. Cho, H. Jang, B.K. Kim, C. Jang, and I.S. Kim, 'Environmental Fatigue Behaviors of SA508 Gr.1a Low Alloy Steel in $310^{\circ}C$ Deoxygenated Water,' Key Eng. Mater., 345-346, 1039 (2007)
H. Cho, H. Jang. B.K. Kim, I.S. Kim, and C. Jang, 'Effect of Cyclic Strain Rate on Environmental Fatigue Behaviors of SA508 Gr.1a Low Alloy Steel in $310^{\circ}C$ Deoxygenated Water,' Adv. Mater. Res., 26-28, 1121 (2007)
H. Cho, B.K. Kim, I.S. Kim and C. Jang, 'Low Cycle Fatigue Behaviors of Type 316LN Austenitic Stainless Steel in $310^{\circ}C$ Deaerated Water - Fatigue Life and Dislocation Structure Development,' Mat. Sci. Eng. A, 476, 248 (2008)
H. Cho, B.K. Kim, I.S. Kim, C. Jang, and D.Y. Jung, 'Fatigue Life and Crack Growth Mechanisms of the Type 316LN Austenitic Stainless Steel in $310^{\circ}C$ Deoxygenated Water,' J. Nucl. Sci. Technol., 44, 1007 (2007)
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S.G. Lee, C. Jang, and I.S. Kim, 'Effects of Hydrogen on the Fatigue Crack Growth Rate of Low Alloy Steels,' Proc. Int. Congress on Advanced Nuclear Power Plant (ICAPP'06), Reno, NV, USA, June 4-8, 2006
J.D. Atkinson, J. Yu, Z.Y. Chen and Z.J. Zhao, 'Modelling of Corrosion Fatigue Crack Growth Plateau for RPV Steels in High Temperature Water,' Nucl. Eng. Des., 184, 13 (1998). 232
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