1993－1997華中理工大學(xué)機(jī)械工程二系博士
1990－1993華中理工大學(xué)機(jī)械工程二系碩士
1986－1990華中理工大學(xué)機(jī)械工程二系學(xué)士

1997－2001，華中理工大學(xué)，材料科學(xué)與工程學(xué)院，講師
2001－2004，日本巖手大學(xué)工學(xué)部，JSPS博士后研究員
2004－2017，上海交通大學(xué)機(jī)械與動(dòng)力工程學(xué)院，副教授
2018 - 現(xiàn)在， 上海交通大學(xué)機(jī)械與動(dòng)力工程學(xué)院，研究員

水冷堆核電站材料腐蝕性能評(píng)價(jià)
材料應(yīng)力腐蝕/腐蝕疲勞機(jī)理研究
核電站設(shè)備老化機(jī)理與失效分析
核反應(yīng)堆水化學(xué)

能源行業(yè)核電標(biāo)準(zhǔn)化技術(shù)委員會(huì)(NEA/TC2)委員
國際第四代核能論壇(GIF)超臨界水冷堆(SCWR)技術(shù)委員會(huì)中國副代表
中國核學(xué)會(huì)教育咨詢委員會(huì)委員

2007―2011    國家973項(xiàng)目“超臨界水堆關(guān)鍵科學(xué)問題的基礎(chǔ)研究”，研究骨干
2009―2011    國家自然科學(xué)基金項(xiàng)目“鎳基690 合金晶界結(jié)構(gòu)優(yōu)化與耐腐蝕性研究”，負(fù)責(zé)人
2009―2010    上海核工程研究設(shè)計(jì)院項(xiàng)目“核電廠二回路碳鋼管道流動(dòng)加速腐蝕性能實(shí)驗(yàn)”，負(fù)責(zé)人
2010―2013    大型先進(jìn)壓水堆核電站重大專項(xiàng)重大共性技術(shù)及關(guān)鍵設(shè)備、材料研究課題“壓水堆核電材料環(huán)境相容性研究”子課題“焊接工藝及焊后熱處理方法對(duì)管道焊接件環(huán)境相容性的影響”，負(fù)責(zé)人
2010―2015    大型先進(jìn)壓水堆核電站重大專項(xiàng)重大共性技術(shù)及關(guān)鍵設(shè)備、材料研究課題“蒸汽發(fā)生器690合金U形管的研制和應(yīng)用性能研究”，研究骨干
2014-2015     大型先進(jìn)壓水堆核電站重大專項(xiàng)“CAP1400水化學(xué)研究”
2014-2015     大型先進(jìn)壓水堆核電站重大專項(xiàng)“690合金管在高溫水環(huán)境下微動(dòng)磨損試驗(yàn)”
2015-2016     日立公司“泵、閥材料氣蝕機(jī)理及可靠性研究”
2017-2018    海洋動(dòng)力裝備構(gòu)件腐蝕疲勞機(jī)理研究，科技部973項(xiàng)目
2017-2020  應(yīng)力-腐蝕-熱時(shí)效耦合環(huán)境核電關(guān)鍵材料服役行為高通量評(píng)價(jià)技術(shù)，科技部重點(diǎn)研發(fā)
2018-2022 晶間碳化物對(duì)鎳基690合金應(yīng)力腐蝕開裂的影響機(jī)理研究，自然科學(xué)基金
2019-2022 超臨界水冷堆材料與化學(xué)研發(fā)，科技部重點(diǎn)研發(fā)國際合作項(xiàng)目

2019
[1] Kai Chen, Jiamei Wang, et al. Effect of intergranular carbides on the cracking behavior of cold worked Alloy 690 in subcritical and supercritical water, Corrosion Science Online 108313.
[2] Kai Chen, Jiamei Wang, et al. Comparison of the stress corrosion cracking growth behavior of cold worked Alloy 690 in subcritical and supercritical water, Journal of Nuclear Materials 520 (2019) 235-244.
[3] Jiamei Wang, Haozhan, Su, Kai Chen*, Donghai Du*, Lefu Zhang*, Yongduo Sun, Corrosion fatigue crack growth behavior of alloy 52?M in high-temperature water, Journal of Nuclear Materials 528 (2020) 151848.
[4] Zhao Shen*, David Tweddle, Mark Thomas Lapington, Benjamin Jenkins, Donghai Du, Lefu Zhang, Michael P. Moodya, Sergio Lozano-Perez, Observation of internal oxidation in a 20% cold-worked Fe-17Cr-12Ni stainless steel through high-resolution characterization, Scripta Materialia 173 (2019) 144-148.
[5] Jiamei Wang, Haozhan, Su, Kai Chen*, Donghai Du, Lefu Zhang, Zhao Shen, Effect of δ-ferrite on the stress corrosion cracking behavior of 321 stainless steel, Corrosion Science 158 (2019) 108079.
[6] Donghai Du*, Jiamei Wang, Kai Chen, Lefu Zhang*, Stress corrosion cracking behavior of warm forged 316L stainless steel at different orientations, Journal of Nuclear Materials 522 (2019) 220-225.
[7] Lefu Zhang, Farzin Arjmand*, Water chemistry, solution resistivity, and oxygen reduction reaction in simulated primary coolant of pressurized water reactors, Materials and Corrosion 70 (2019) 1179-1191.
[8] Farzin Arjmand, Jiamei Wang, Lefu Zhang*, Zinc addition and its effect on the corrosion behavior of a 30% cold forged Alloy 690 in simulated primary coolant of pressurized water reactors, Journal of Alloys and Compounds 791 (2019) 1176-1192.
[9] Xianglong Guo*, Yi Fan, Wenhua Gao, Rui Tang, Kai Chen, Zhao Shen, Lefu Zhang*, Corrosion resistance of candidate cladding materials for supercritical water reactor, Annals of Nuclear Energy 127 (2019) 351-363.
[10] Ping Lai, Hao Zhang, Lefu Zhang, Qifeng Zeng, Junqiang Lu, Xianglong Guo*, Effect of micro-arc oxidation on fretting wear behavior of zirconium alloy exposed to high temperature water, Wear 424-425 (2019) 53-61.
[11] Zhao Shen*, Donghai Du*, Lefu Zhang, Sergio Lozano-Perez, An insight into PWR primary water SCC mechanisms by comparing surface and crack oxidation, Corrosion Science, 148 (2019) 213-227.
[12] Zhao Shen, Kai Chen, Xianglong Guo, Lefu Zhang*, A study on the corrosion and stress corrosion cracking susceptibility of 310-ODS steel in supercritical water, Journal of Nuclear Materials 514 (2019) 56-65.
[13] Donghai Du, Jiamei Wang, Kai Chen*, Lefu Zhang*, Peter L. Andresen, Environmentally assisted cracking of forged 316LN stainless steel and its weld in high temperature water, Corrosion Science 147 (2019) 69-80.

2018
[1]. Lefu ZHANG, Jiamei WANG, Farzin ARJMAND, Electrochemical Behavior of Alloy 825 at High Temperature Pressurized Water Chloride Solutions (30°C to 280°C), Corrosion 74 (2018) 1245-1258
[2]. 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.
[3]. Kai Chen, Jiamei Wang, et al. Investigation on the stress corrosion crack initiation and propagation behavior of Alloy 600 in high temperature water, Corrosion 74 (2018) 1395-1405.
[4]. 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.
[5]. 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.
[6]. 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.
[7]. 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.
[8]. 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
[9]. 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.
[10]. 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.
[11]. 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.
[12]. 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
[13]. Zhang L, Wang J. et al. High Temperature Electrochemical Corrosion Behavior of Fe-Cr-Ni Alloys in Simulated PWR water. CORROSION, 74(2018) 415-423.

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2017.08.01 國家發(fā)明專利授權(quán)
專利授權(quán)號(hào)：ZL 2014 1 0682423.6
2 一種在線檢測金屬減薄速率的試樣及方法 授權(quán)日
2017．07．11 國家發(fā)明專利授權(quán)
專利授權(quán)號(hào)：ZL 2014 1 0820618.2