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      Xiangyu Zhong, En-Hou Han, Xinqiang Wu, Corrosion behavior of Alloy 690 in aerated supercritical water, Corrosion Science, 66 (2013) 369-379
      Haitao Wang, En-Hou Han, Simulation of metastable corrosion pit development under mechanical stress, Electrochimica Acta, 90 (2013) 128-134
      Yingwei Song, Dayong Shan, En-Hou Han, A novel biodegradable nicotinic acid/calcium phosphate composite coating on Mg-3Zn alloy, Materials Science & Engineering C 2013(33)78-84.
      J. Xu, X. Q. Wu, E. H. Han, Acoustic emission response of sensitized 304 stainless steel during intergranular corrosion and stress corrosion cracking, Corros. Sci., 73, 2013, 262-273.
      X. Liu, X. Q. Wu, E. H. Han, Electrochemical and surface analytical investigation of the effects of Zn concentrations on characteristics of oxide films on 304 stainless steel in borated and lithiated high temperature water, Electrochimica Acta, 2013, doi: 10.1016/j.electacta.2013.06.131.
      X. Q. Wu, E.-H. Han, Y.M. Xu, Nuclear Power Development and Major Research Projects in China, Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia, 2013, October 14-17, 2013, Taichung, Taiwan, Plenary Talk. (Plenary talk)
      X. Q. Wu, W. J. Kuang, E.-H. Han, W. Ke, Y. Tang, T. C. Dan, Characteristics of Oxide Films on Nickel-base Alloy 690 Exposed to Oxygenated High Temperature Pure Water, Proceedings of Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia, 2013, October 14-17, 2013, Taichung, Taiwan
      J. B. Tan, X. Q. Wu, En-Hou Han, X.Q. Liu, X.L. Xu, F.J. Meng, Corrosion fatigue behavior of Alloy 690 tubing in a pressurized water reactor environment, 3rd International Symposium on Materials and Reliability in Nuclear Power Plants, September 14-17, 2013, Shenyang, China, pp. 45
      X. Q. Wu, W. J. Kuang, En-Hou Han, Wei Ke, Oxidation corroison characterisitics of nuclear-grade stainless steel and Ni-base alloy in oxygenated high temperatrue pure water, 3rd International Symposium on Materials and Reliability in Nuclear Power Plants, September 14-17, 2013, Shenyang, China, pp. 21.
      J. Li, X. Q. Wu, E.-H. Han, Microstruture and corrosion behavior of the fusion boundary region of domestic low alloy steel SA-508-III weld joint in borated and lithiated high temperature water, 3rd International Symposium on Materials and Reliability in Nuclear Power Plants, September 14-17, 2013, Shenyang, China, pp. 37.
      Q. Guo, X. Q. Wu, E.-H. Han, Response to pH value and corrsponding mechanism of different kinds of tungsten/tungsten oxide electrodes, 3rd International Symposium on Materials and Reliability in Nuclear Power Plants, September 14-17, 2013, Shenyang, China, pp. 48.
      X. H. Liu, X. Q. Wu, E.-H. Han, Effects of Zn injection on the stress corrosion cracking behavior of senstitized stainless steel in borated and lithiated high temperature water, 3rd International Symposium on Materials and Reliability in Nuclear Power Plants, September 14-17, 2013, Shenyang, China, pp. 32.
      D. X. Chen, X. Q. Wu, E.-H. Han, Crevice corrosion study on nuclear-grade 304 stainless steel in high temperature and high pressure water, 3rd International Symposium on Materials and Reliability in Nuclear Power Plants, September 14-17, 2013, Shenyang, China, pp. 38.
      吴欣强,韩恩厚,柯伟,核电材料高温高压水腐蚀疲劳行为与环境疲劳设计模型,2013年核电厂老化与寿命管理研讨会会议论文集,武汉,中国,2013年11月12-13日,PP. 65.
      陈东旭,吴欣强,韩恩厚,核级304不锈钢高温水环境缝隙腐蚀研究,第七届全国腐蚀大会论文摘要集,长垣, 中国,2013年7月27-28日,pp. 155
      郭琦,吴欣强,不同钨/氧化钨电极的pH响应及机理研究,第七届全国腐蚀大会论文摘要集,长垣, 中国,2013年7月27-28日,pp. 21.
      谭季波,吴欣强,韩恩厚,柯伟,国产核级316L不锈钢在高温高压水中腐蚀疲劳裂纹起始及扩展特征,第七届全国腐蚀大会论文摘要集,长垣, 中国,2013年7月27-28日,pp. 154. (优秀报告奖)
      吴欣强,匡文军,韩恩厚,柯伟,核级不锈钢和镍基合金高温高压水腐蚀产物膜特征,第七届全国腐蚀大会论文摘要集,长垣, 中国,2013年7月27-28日,pp. 157.
      李江,吴欣强,韩恩厚,国产SA508-3同种金属焊后微观结构及腐蚀行为研究,第七届全国腐蚀大会论文摘要集,长垣, 中国,2013年7月27-28日,pp. 42.
      刘侠和,吴欣强,韩恩厚,温度和pH值变化对加Zn高温水环境中国产核级316L不锈钢的电化学腐蚀性能影响,第七届全国腐蚀大会论文摘要集,长垣, 中国,2013年7月27-28日,pp. 97.
      Jianqiu Wang, Fa Huang, En-Hou Han, and Fanjiang Meng (2013) Microscopic Residual Stresses Beneath a Scratch and Their Effects on Scratch-Related Crack Initiation of Thermally Treated UNS N06690 in High-Temperature Pressurized Water. Corrosion: September 2013, Vol. 69, No. 9, pp. 893-899.
      张利涛,王俭秋, 国产锻造态核级316L不锈钢在高温高压水中的应力腐蚀裂纹扩展行为, 金属学报, 2013, 49(8), 911-916
      Fa Huang, Jianqiu Wang, En-Hou Han, Wei Ke, Microstructural characteristics of the oxide films formed on Alloy 690TT in pure and primary water at 325 C, Corrosion Science, 2013, 76, 52-59
      Xiaohui Li, Jianqiu Wang, En-Hou Han, Wei Ke, Corrosion behavior for Alloy 690 and Alloy 800 tubes in simulated primary water, Corrosion Science, 2013, 67, 169-178