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汪家梅
助理研究员
所在系所:核科学与工程学院
办公电话:
通讯地址:上海交通大学机械与动力工程学院B楼
电子邮件:wangjiamei@sjtu.edu.cn
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教育背景
2017.04-2020.12 上海交通大学, 核科学与技术,博士,导师:张乐福 & Peter. L. Andresen
2014.06-2017.03 上海交通大学, 核工程与技术,硕士,导师:张乐福
2010.09-2014.06 上海理工大学,热能与动力工程,学士
工作经历
研究方向
核反应堆结构材料腐蚀及开裂失效行为评价、服役寿命预测及水化学策略研究,包括:
以不锈钢、镍基合金和锆合金为代表的反应堆结构材料的腐蚀、开裂失效行为与机理研究
以超临界水冷堆、小型模块化反应堆为代表的先进反应堆候选结构材料的腐蚀、开裂失效行为研究
以新型不锈钢、增材制造合金和高熵合金为代表的反应堆新型结构材料的腐蚀、开裂失效行为与机理研究
反应堆结构材料服役行为及寿命预测
反应堆材料-水化学相容性评价、水化学策略研究
先进的材料表征技术的应用
科研项目
校企合作项目(成都核动力院):板弹簧应力腐蚀开裂研究(2022.03-2023.06,在研,项目负责人)
校企合作项目(中广核研究设计院):一回路注锌安全验证实验服务(2021.09-2022.10,在研,项目技术负责人)
十四五预研基金(成都核动力院):核动力堆停役去污方案及计算模型研究(2022.03-2023.09,在研,项目技术负责人)
国家自然科学基金:晶界碳化物对690合金应力腐蚀开裂的影响机理研究(课题编号5187010234);(2019.01-2022.01,在研,研究骨干)
国家重点研发计划:超临界水冷堆核能系统材料与化学研发(课题编号2018YFE0116200);(2019.11-2022.10,在研,研究骨干)
校企合作项目(生态环境部核与辐射安全中心):奥氏体不锈钢管道焊缝应力腐蚀开裂影响因素阈值敏感性试验(2020.12-2021.12,结题,独立完成)
国家重点研发计划:应力-腐蚀-热时效耦合环境核电关键材料服役行为高通量评价技术(课题编号2017YFB0702203);(2017.09-2021.08,结题,主要完成人)
装备预研重点实验室基金(中国核动力院):核动力堆主设备材料应力腐蚀行为及寿命预测模型研究(课题编号6142A0603011706);(2018.01-2019.09,结题,主要完成人)
国际间合作项目(ICG-EAC):Round Robin on Stress Corrosion Cracking Initiation in Alloy 600.(2018.06-2019.08,结题,主要完成人)
代表性论文专著
[1] Jiamei Wang, Tianyu Zhu, Kai Chen, Yichen Bao, Wujiang Ma, Miaomiao Zhang, Xianglong Guo, Peter L. Andresen, Lefu Zhang, Investigations on the SCC initiation behavior of cold worked 316 L in high temperature oxygenated water at constant loads, Corrosion Science, 2022, 203, 110336.
[2] Jiamei Wang, Haozhan Su, Kai Chen, Lefu Zhang*. Effect of δ-ferrite on the stress corrosion cracking behavior of 321 stainless steel. Corrosion Science, IF=7.2, 2019, 158: 108079.
[3] Jiamei Wang, Tianyu Zhu, Yaolei Han, Jinna Mei, Fei Xue, Kai Chen*, Donghai Du, Peter L. Andresen, Lefu Zhang*, Miaomiao Zhang. Environment assisted cracking of 308L weld metal in high temperature water, Journal of Nuclear Materials, 2021, 557(9).
[4] Jiamei Wang, Tianyu Zhu, Kai Chen, Donghai Du, Peter L. Andresen, Lefu Zhang*, Effect of dissolved oxygen and hydrogen on the stress corrosion cracking behavior of alloy 600 in high temperature water, Journal of Nuclear Materials, 2021, 543:152603.
[5] Jiamei Wang, Haozhan Su, Kai Chen, Lefu Zhang*. Corrosion fatigue crack growth behavior of alloy 52 M in high-temperature water. Journal of Nuclear Materials, 2020, 528: 151848.
[6] Jiamei Wang, Haozhan Su, Arjmand Farzin, Lefu Zhang*. Effects of Corrosion Potential, Dissolved Oxygen, and Chloride on the Stress Corrosion Cracking Susceptibility of a 316NG Stainless Steel Weld Joint. Corrosion, 2019, 75(8): 946-959. (SCI)
[7] Jiamei Wang, Hui Lu, Lefu Zhang*. Effects of dissolved gas and cold work on the electrochemical behaviors of 304 stainless steel in simulated PWR primary water. Corrosion, 2017, 73(3): 281-289. (SCI)
[8] 汪家梅,朱天语,鲍一晨,刘晓强,陈凯,张乐福*,郑会,杨双亮. 溶解氧和溶解氢对冷变形690 MA合金应力腐蚀开裂的影响规律[J]. 原子能科学技术,2021,55(06):1067-1074. (EI)
[9] 汪家梅,苏豪展,何琨,张乐福*. 电位对508Ⅲ-52M-690合金焊接接头应力腐蚀的影响[J]. 上海交通大学学报,2018,52(04):447-454. (EI)
[10] 汪家梅, Farzin Arjmand,杜东海,陈凯,赖平,高文华,张浩,郭相龙,张乐福*. 压水堆一回路主管道316L不锈钢的电化学腐蚀行为[J]. 工程科学学报,2017,39(09):1355-1363. (EI)
[11] 汪家梅,段振刚,张乐福*,孟凡江,石秀强. 核电蒸汽发生器690合金管在高温高压水中的腐蚀电化学行为[J].上海交通大学学报,2016,50(04):514-520. (EI)
[12] Kai Chen*, Jiamei Wang, Zhao Shen, Donghai Du, Xianglong Guo, Lefu Zhang*, Peter L. Andresen, Effect of intergranular carbides on the cracking behavior of cold worked Alloy 690 in subcritical and supercritical water, Corrosion Science, IF=7.2, 2019, 164: 108313.
[13] 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, IF=6.5, 2019, 158: 66-70.
[14] 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[J]. Journal of Alloys and Compounds, IF=5.3, 2019, 791: 1176-1192.
[15] Kai Chen, Jiamei Wang, Zhao Shen, Donghai Du, Xianglong Guo, Bin Gong, Jinhua Liu, Lefu Zhang*, Comparison of the stress corrosion cracking growth behavior of cold worked Alloy 690 in subcritical and supercritical water, Journal of Nuclear Materials, 2019,520: 235-244.
[16] 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, 2018, 503: 13-21.
[17] Kai Chen, Jiamei Wang, Haozhan Su, Lefu Zhang*, Investigation on the stress corrosion crack initiation and propagation behavior of Alloy 600 in high temperature water, Corrosion, 2018, 74 :1395-1405. (SCI)
[18] Kai Chen, Jiamei Wang, Donghai Du*, Xianglong Guo*, Lefu Zhang, Peter L. Andresen, Stress corrosion crack growth behavior of 310S stainless steel in supercritical water, Corrosion, 2018, 74 :776-787. (SCI)
荣誉奖励
2019年 上海交通大学赵朱木兰奖学金(一等)
2018年 中国核动力博士生奖学金(一等)
2017年 上海市:上海市优秀毕业生
2017年 上海交通大学优秀硕士论文
2016年 教育部:研究生国家奖学金