教育经历  

2014-09 至 2019-06,中国科学院大学,材料科学与工程,博士

2010-09 至 2014-07,中国石油大学（华东）,材料科学与工程,学士

工作经历

2024-09 至 今,中国科学院金属研究所,腐蚀基础与前沿研究部,项目研究员

2021-09 至 2024-09,中国科学院金属研究所,腐蚀基础与前沿研究部,副研究员

2019-07 至 2021-09,中国科学院金属研究所,腐蚀基础与前沿研究部,助理研究员

核电关键材料的服役行为（腐蚀疲劳、热疲劳、污垢沉积）

　　澄清了材料、力学、水化学等因素影响核电设备材料服役行为与损伤机制。建立了核电设备材料在模拟冷却剂环境中的疲劳寿命及疲劳裂纹扩展模型，已形成标准用于国产核电站设计、运行及寿命管理；建立了核电设备材料在模拟压水堆一回路冷却剂中的腐蚀、释放及污垢沉积模型，为我国核电技术的“自主化”与“走出去”提供了有力支撑。

◆中国核工业集团有限公司“菁英人才”（2024）

◆中国科学院沈阳分院优秀青年科技人才（2024）

◆金属研究所“青年学者论坛”二等奖（2022）

◆中国核工业集团有限公司“启明星人才”（2020）

1)Yongjian Ma,Ziyu Zhang*,Jibo Tan et al. Microstructurally and mechanically small fatigue crack growth behaviors of 316LN stainless steel in high-temperature pressurized water,Corrosion Science 227 （2024）111735

2)Chaochao Xue,Xiaohan Liu,Zhongcun Chen,Ziyu Zhang*,et al. Effects of Zn injection on the oxide film characteristics of zirconium alloy fuel cladding exposed to high-temperature pressurized water with or without subcooled nucleate boiling,Journal of Nuclear Materials  599(2024)155210

3)Chaochao Xue,Ziyu Zhang*,Jibo Tan,et al. Effects of Zn injection on corrosion behavior and crud deposition of FeCrAl fuel cladding under subcooled nuclear boiling condition in high-temperature pressurized water,Corrosion Science  211(2023)110909

4)Fangqiang Ning,Jibo Tan,Ziyu Zhang*,et al. Crevice corrosion behaviors of Alloy 690 and 405 stainless steel in chloride solutions with different concentrations of thiosulfate,Journal of Nuclear Materials 575(2023)154226

5)Yongjian Ma,Ziyu Zhang*,Jibo Tan et al. Effect of surface roughness on low-cycle fatigue behaviors of 316LN stainless steel in borated and lithiated high-temperature pressurized water,Corrosion Science 209 (2022) 110792

6)Yongjian Ma;Ziyu Zhang*;Xu Zhang;Haifeng Yin;Bingbing Liang;Jibo Tan;Xinqiang Wu;En-Hou Han;Wei Ke;Effects of strain rate on low-cycle fatigue crack growth behavior of 316LN weld metal in high-temperature pressurized water,Corrosion Science,2022,199

7)Chaochao Xue,Yulong Mao,Ziyu Zhang*,et al. Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments,Journal of Nuclear Materials 568 (2022) 153899

8)Ziyu Zhang;Jibo Tan;Xinqiang Wu;En-Hou Han;Wei Ke;Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water,Nuclear Engineering and Technology,2021,53(9):2977-2981

9)Ziyu Zhang;Jibo Tan;Xinqiang Wu;En-Hou Han;Wei Ke;Jiancun Rao;Corrosion fatigue behavior and crack-tip characteristic of 316LN stainless steel in high-temperature pressurized water,Journal of Nuclear Materials,2019,518: 21-29

10)Ziyu Zhang;Jibo Tan;Xinqiang Wu;En-Hou Han;Wei Ke;Jiancun Rao;Effects of temperature on corrosion fatigue behavior of 316LN stainless steel in high-temperature pressurized water,Corrosion Science,2019,146: 80-89

11)韩恩厚,张兹瑜,吴欣强等. 核电厂金属材料高温高压水中腐蚀疲劳裂纹扩展试验方法,核学会团体标准,T/CNS 19-2020

12)张兹瑜,薛超超,廖家鹏等. 核电厂一回路水环境燃料包壳污垢沉积试验方法,核学会团体标准,T/CNS 75-2022