1993－1997, Huazhong University of Science and Technology, Doctor
1990－1993, Huazhong University of Science and Technology, Master
1986－1990, Huazhong University of Science and Technology, Bachelor

1997-2001, Lecturer, Huazhong University of Science and Technology
2001-2004, JSPS Post Doc, Faculty of Engineering, Iwate University
2004-2017, Associate Prof. School of Mechanical and Power Engineering, Shanghai Jiao Tong University
2018-now, Prof. School of Nuclear Engineering, Shanghai Jiao Tong University

2007-now, Director, Joint Laboratory for Corrosion of Nuclear Power Materials, between Shanghai Jiao Tong University and Shanghai Nuclear Engineering and Design Institute.
2014~Now, Director of research Center, Shanghai Xinmin Heavy forging Co. Ltd.

Stress corrosion and corrosion fatigue of reactor materials
Failure analysis of nuclear power components
PWR water chemistry

Stress corrosion and corrosion fatigue research and evaluation of reactor materials, such as alloy 690, stainless steels and low carbon low alloy steels

Application of Grainboundary engineering to improve the corrosion resistance of nickel base alloys and austenitic stainless steels

Corrosion evaluation and materials development of supercritical water-cooled reactor

Flow accelerated corrosion of carbon steel pipes in secondary loops of nuclear power plants

[1]. Kai Chen, Jiamei Wang, Donghai Du*, Xianglong Guo, Lefu Zhang*. Characterizing the effects of in-situ sensitization on stress corrosion cracking of austenitic steels in supercritical water, Scripta Materialia. 158 (2019) 66-70.
[2]. Kai Chen, Jiamei Wang, et al. Investigation on the stress corrosion crack initiation and propagation behavior of Alloy 600 in high temperature water, Corrosion. online published.
[3]. Kai Chen, Jiamei Wang, Donghai Du, Xianglong Guo, Peter L. Andresen, Lefu Zhang*. Stress corrosion crack growth behavior of 310S stainless steel in supercritical water, Corrosion 74 (2018) 776-787.
[4]. Kai Chen, Jiamei Wang, Donghai Du, Peter L. Andresen, Lefu Zhang*. dK/da effects on the SCC growth rates of nickel base alloys in high-temperature water, Journal of Nuclear Materials 503 (2018) 13-21.
[5]. Xianglong Guo, Kai Chen, Wenhua Gao, Zhao Shen, Lefu Zhang*. Corrosion behavior of alumina-forming and oxide dispersion strengthened austenitic 316 stainless steel in supercritical water. Corrosion Science 138 (2018) 297-306.
[6]. Xianglong Guo, Ping Lai, Lichen Tang, Kai Chen, Lefu Zhang. Time-dependent wear behavior of alloy 690 tubes fretted against 405 stainless steel in high temperature argon and water. Wear, in press.
[7]. Xianglong Guo, Wenhua Gao, Kai Chen, Zhao Shen, Lefu Zhang*. Corrosion and stress corrosion cracking susceptibility of 347H stainless steel in supercritical water. Corrosion, 2018, 74(1): 227-236
[8]. Xianglong Guo*, Ping Lai, Lichen Tang, Junqiang Lu, Jiamei Wang, Lefu Zhang*. Fretting wear of alloy 690 tube mated with different materials in high temperature water, Wear 400-401 (2018) 119-126.
[9]. Kai Chen, Donghai Du, Wenhua Gao, Xianglong Guo, Lefu Zhang*, Peter L. Andresen. Effect of cold work on the stress corrosion cracking behavior of Alloy 690 in supercritical water environment, Journal of Nuclear Materials 498 (2018) 117-128.
[10]. Lefu Zhang, Ping Lai, Qingdong Liu, Qifeng Zeng, Junqiang Lu, Xianglong Guo*. Fretting wear behavior of zirconium alloy in B-Li water at 300℃. Journal of Nuclear Materials 499 (2018) 401-409.
[11]. Ping Lai, Xiaochuan Gao, Lichen Tang, Xianglong Guo*, Lefu Zhang. Effect of temperature on fretting wear behavior and mechanism of alloy 690 in water, Nuclear Engineering and Design 327 (2018) 51-60
[12]. Zhang L, Wang J. et al. High Temperature Electrochemical Corrosion Behavior of Fe-Cr-Ni Alloys in Simulated PWR water. CORROSION, 2018.

Reactor materials, 54 hours course for graduate students
Introductions to Nuclear Engineering, 18 hours course for undergraduate students
Reactor materials and Water chemistry, 18 hours course for undergraduate students

Preparation of high performance zirconia powder, Patent No.02115615.8

Techical board Member of Technical commission 2 of Nuclear Engineering Association
Project Management Board mumber of supercritical water cooled reactor (SCWR) steering committee in GIF