論文- 庄子 哲雄 -
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件数:553件
[2009]
101.Microstructure, Mechanical Property and Stress Corrosion Cracking of the Fusion Boundary Region in an Alloy 182-Low Alloy Steel Dissimilar Weld Joint in High Temperature Oxygenated Water.[第56回材料と環境討論会講演集,(2009)]Q.J. Peng, J. Hou, Y. Takeda, J. Kuniya, T. Shoji
102.Effect of Overload on SCC Growth in Stainless Steels in High Temperature Water.[日本保全学会第6回学術講演会要旨集,(2009)]He XUE, Q.J. Peng, Tetsuo SHOJI
103.Effects of loading mode and water chemistry on stress corrosion cracking of 316L stainless steel in simulated PWR environments.[14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors,(2009)]Tetsuo Shoji, Zhanpeng Lu, Seiya yamazaki
104.Quantifying the effects of strain-hardening and water chemistry on crack growth rates of 316L SS welds in high temperature water.[International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors,(2009)]Zhanpeng Lu, Kazuhiko Sakaguchi, Koji Negishi, Yoichi Takeda, Yuzuru Ito, Tetsuo Shoji
105.The effect of strain-hardening on PWSCC of Nickel-base Alloys 600 and 690.[International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors,(2009)]Tetsuo Shoji, Zhanpeng Lu, Seiya yamazaki
106.Investigation of the Effect of Dissolved Hydrogen on the Oxide Film on Alloy 600 in High Temperature Water by In-situ Electrochemical Techniques.[日本保全学会第6回学術講演会要旨集,(2009)]Q.J. Peng, Y. Takeda, J. Kuniya, T. Shoji
107.A Study of Microstructure in an Alloy 182/Low Alloy Steel Dissimilar Weld Joint.[日本保全学会第6回学術講演会要旨集,(2009)]J. Hou, Q.J. Peng, J. Kuniya, T. Shoji
108.Effects of Dissolved Hydrogen on the Electronic Properties of the Oxide Film on Alloy 600 in High Temperature Water.[14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors,(2009)]Q.J. Peng, Y. Takeda, J. Kuniya, T. Shoji
109.高温水中におけるオーステナイト系合金の高応力下酸化-2 表面硬化層の影響評価.[日本保全学会第6回学術講演会,(2009)]竹田陽一、佐藤崇之、庄子哲雄、大地昭生
110.高温水中におけるオーステナイト系合金の高応力下酸化-1 Cr含有量の影響評価.[日本保全学会第6回学術講演会,(2009)]佐藤崇之、竹田陽一、庄子哲雄、大地昭生
111.The effect of strain-hardening on PWSCC of Nickel-base Alloys 600 and 690.[14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors,(2009)]Tetsuo Shoji, Zhanpeng Lu, Seiya yamazaki
112.Quantifying the effects of strain-hardening and water chemistry on crack growth rates of 316L SS welds in high temperature water.[14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors,(2009)]Q.J. Peng, Y. Takeda, J. Kuniya, T. Shoji
113.Quantum chemical molecular dynamics study of strain effect on the oxygen diffusion in fcc Fe (111) and Fe-Cr (111) surfaces at 288 0C.[12th International Conference on Fracture, Ottawa, Canada,(2009)]N. K. Das, T. Shoji, K. Suzuki, and Y. Takeda
114.Effect of uneven crack front on crcak tip mechanics and the implication to stress corrosion crack growth.[ASME 2009 Pressure Vessel and Piping Conference,(2009)]He Xue, Zhanpeng Lu, Hiroyoshi Murakami, Tetsuo Shoji
115.Locally delaminating stress corrosion cracking growth of strain-hardened austenitic alloys in hydrogenated high temperature water environments.[ASME 2009 Pressure Vessel and Piping Conference,(2009)]Zhanpeng Lu, He Xue, Hiroyoshi Murakami, Tetsuo Shoji
116.Modeling stress corrocion cracking growth rates based upon the effect of stress/strain on crack tip interface degradation and oxidation reaction kinetics.[ASME 2009 Pressure Vessel and Piping Conference,(2009)]Tetsuo Shoji, Zhanpeng.Lu, Nishith Kumar Das, Hiroyoshi Murakami, Yoichi Takeda, Ismail Tirtom
117.Proactive Materials Degradation Management Program in Japan.[American Nuclear Society 2009 Annual Meeting,(2009)]T. Shoji, Y. Takeda, Q. Peng, J. Kuniya, F. P. Ford and P. M. Scott
118.Quantifying the Effects of Loading Mode and Dissolved Hydrogen Concentration on Crack Growth of Cold Worked Stainless Steels in Simulated PWR Environments.[JSCE Materials and Environments 2009, Tokyo, Japan,(2009)]Zhanpeng Lu, Seiya Yamazaki, Tetsuo Shoji
119.Stress corrosion cracking growth behavior of strain hardened 316L SS and weld transition zone in high temperature water.[JSCE Materials and Environments 2009, Tokyo, Japan,(2009)]Zhanpeng Lu, Koji Negishi, Juan Hou, Yoichi Takeda, Tetsuo Shoji
120.Effect of welded mechanical heterogeneity on local stress and strain ahead of stationary and growing crack tips.[Nuclear Engineering and Design,239(4),(2009),628-640]He Xue, Kazuhiro Ogawa, Tetsuo Shoji
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