080502-材料学

核电材料的环境损伤与寿命预测
核电材料的环境损伤与寿命预测

1995-03--1999-07   清华大学   工学博士
1992-09--1995-03   天津大学   工学硕士
1986-09--1990-07   四川大学（原成都科技大学）   工学学士

   

2011-04~现在, 中国科学院金属研究所, 研究员
2007-01~2011-03,日本东北大学能源安全科学国际研究中心, 客座副教授、副教授
2004-07~2006-07,美国密西根大学核工程与放射科学系, Research Fellow
1999-07~2004-06,日本东北大学断裂研究所, 博士后研究员、日本学术振兴会特别研究员
1995-03~1999-07,清华大学, 工学博士
1992-09~1995-03,天津大学, 工学硕士
1986-09~1990-07,四川大学（原成都科技大学）, 工学学士

   

（1） Effect of Dissolved Hydrogen on Corrosion of Inconel Alloy 600 in High Temperature Hydrogenated Water, Electrochimica Acta, 2011, 第 1 作者
（2） Effects of cold working path on strain concentration, grain boundary microstructure and stress corrosion cracking in Alloy 600, Corrosion Science, 2011, 第 2 作者
（3） Effects of deformation degrees on grain boundary characters and strain concentration on grain boundaries in Nickel-base Alloy 600, Corrosion Science, 2011, 第 2 作者
（4） Microstructure and stress corrosion cracking of the fusion boundary region in an Alloy 182-A533B low alloy steel dissimilar weld joint, Corrosion Science, 2010, 通讯作者
（5） Microstructure and mechanical property of the fusion boundary region in an Alloy 182-low alloy steel dissimilar weld joint, Journal of Materials Science, 2010, 通讯作者
（6） Residual strain measurement and grain boundary characterization in the heat affected zone of a weld joint between Alloy 690TT and Alloy 52, journal of nuclear materials, 2010, 通讯作者
（7） Effect of Hydrogen in Inconel Alloy 600 on Corrosion in High Temperature Oxygenated Water, Corrosion Science, 2010, 通讯作者
（8） Environmentally-assisted cracking behavior in the transition region of an Alloy182/SA 508 Cl.2 dissimilar metal weld joint in simulated boiling water reactor normal water chemistry environment, Journal of Neclear Materials, 2008, 第 4 作者
（9） Intergranular Environmentally Assisted Cracking of Alloy 182 Weld Metal in Simulated Normal Water Chemistry of Boiling Water Reactor, Corrosion Science, 2007, 第 1 作者
（10） Stress Corrosion Crack Growth in 316 Stainless Steel in Supercritical Water, Corrosion, 2007, 第 1 作者
（11） Facility for Stress Corrosion Cracking of Irradiated Specimens in Supercritical Water, Journal of Nuclear Materials, 2007, 第 2 作者
（12） Corrosion Behavior of Model Zirconium Alloys in Deaerated Supercritical Water at 500C, Corrosion, 2007, 第 1 作者
（13） An ATEM Study of Oxidation Behavior of SCC Crack Tips in 304L Stainless Steel in High Temperature Oxygenated Water, Journal of Nuclear Materials, 2005, 第 2 作者
（14） Development of a Fundamental Crack Tip Strain Rate Equation and its Application to Quantitative Prediction of Stress Corrosion Cracking of Stainless Steels in High Temperature Oxygenated Water, Journal of Nuclear Materials, 2004, 第 1 作者
（15） Effects of Dissolved Hydrogen on the Primary Water Stress Corrosion Cracking Behavior of Alloy 600 at 325C, Key Engineering Materials, 2004, 第 1 作者
（16） Investigation of Dendrite Boundary Chemistry in Alloy 182 using Auger Electron Spectroscopy Analysis, Metallurgical and Materials Transactions A, 2003, 第 1 作者
（17） The Crack Tip Solution Chemistry in Sensitized Stainless Steel in Simulated Boiling Water Reactor Water Studied Using a Microsampling Technique, Journal of Nuclear Science and Technology, 2003, 第 1 作者

   

（1）Microstructure and Stress Corrosion Cracking of the Fusion Boundary Region in an Alloy 182-Low Alloy Steel Dissimilar Weld Joint   Q.J. Peng, J. Hou, Y. Takeda, J. Kuniya, T. Shoji    2010-04-13
（2） Effects of Dissolved Hydrogen on the Electronic Properties of the Oxide Film on Alloy 600 in High Temperature Water,   Q.J. Peng, Y. Takeda, J. Kuniya, T. Shoji   2009-08-23
（3）Characteristic Distance of the Crack Tip Strain Rate Formulation for Quantification of the Stress Corrosion Crack Growth Rate   QJ.. Peng, Y. Takeda, Z. Lu, J. Kuniya, T. Shoji   2008-04-20
（4）SCC Behavior in the Transition Region of an Alloy 182-SA 508 Cl.2 Dissimilar Weld Joint under Simulated BWR-NWC Conditions   Q. J. Peng, T. Shoji, S. Ritter, H-P Seifert   2005-08-14