基本信息

姓名  王达

性别   男

联系邮箱  wangd253@mail.sysu.edu.cn

学科方向  核燃料循环与材料

研究方向 材料腐蚀失效行为与机理研究；耐磨耐蚀表面防护技术研究  

学习经历

2019.12—2020.12  弗吉尼亚理工大学(美国)  机械工程学院  核材料与燃料循环中心  联合培养博士  导师：张金锁

2015.9—2021.6  华北电力大学  核科学与工程学院  核电与动力工程   工学博士  导师：牛风雷

2011.9—2015.7  华北电力大学  核科学与工程学院  核工程与核技术  工学学士

科研项目 

中央高校基本业务经费, 中山大学青年教师培育项目，24qnpy045，结题，负责人；

国家自然科学基金委员会，青年基金，12305199，在研，负责人；

广东省基础与应用基础研究基金区域联合基金，青年基金，2022A1515110802，在研，负责人；

广东省自然科学基金，面上项目，2023A1515011596，在研，负责人 ；

中国博士后科学基金会，第72批面上资助二等，2022M723582，结题，负责人；

国家科技重大专项课题“大型先进压水堆核电站”外协项目，LOCA事故安全壳碎片对燃料组件压降影响试验，ZB12W04，470万，2016-2019，结题，项目骨干；

国家重点研发计划课题子项目，液态金属锂基础物性研究，2018YFB1900602，2019-2022，结题，参与；

代表性学术论文

X.F. Ma, C.Q. Xiao, W.J. zhu, D. Wang*, et. al. Microstructure and corrosion performance of laser-cladded AlCrFeNiNb high-entropy alloy coating on 316L steel in liquid lead-bismuth eutectic. Intermetallics, 2025, 184: 108852.

B.H. Sun, S.R. Liu, C.Q. Xiao, W.J. Zhu, D. Wang*，et. al. Insights into the effect of plasma nitriding on corrosion behavior of 304 stainless steel in liquid lead-bismuth eutectic. Mater. Chem. Phys., 2025, 339: 130790.

D. Wang, B.H. Sun, W.Q. Zhuo, et. al. Microstructure and corrosion behavior of CrAl-coated 316L steel in static and flowing liquid lead-bismuth eutectic. Vacuum, 2025, 233: 114021.

D. Wang, S.R. Liu, C.Q. Xiao, et al. Tensile and cracking behavior of thin-walled 316Ti austenitic steel after exposure to 550 °C lead-bismuth eutectic with different oxygen concentration. J. Mater. Res. Technol., 2024, 33: 5528-5542.

D. Wang, W.Q. Zhuo, S.R. Liu, et al. Microstructure and corrosion property evolution of a surface-nanostructured 15-15Ti austenitic steel during immersion in liquid LBE at 550 °C. J. Nucl. Mater., 2025, 603:155475.

S.R. Liu, W.J. Zhu, Y.J. Li, X.F. Ma*, D. Wang*. New insights into selective leaching and ferritization in 15-15Ti austenitic steel in lead-bismuth eutectic through parent phase reconstruction. Scripta Mater., 2025, 254:116316.

S.R. Liu, B.H. Sun, C.Q. Xiao, D. Wang*, et al. New insights into the corrosion mechanism of 316Ti austenitic steel exposed to 550 ℃ lead-bismuth eutectic with 5×10-6 wt.% and 5×10-7 wt.% oxygen concentration. Corros. Sci., 2024, 240: 112449. 

D. Wang, S.R. Liu, X.F. Ma*, et al. Enhanced corrosion resistance of 15-15Ti austenitic steel in liquid lead-bismuth eutectic at 550 ℃ by shot peening processing. Corros. Sci., 2024, 226: 111640.

D. Wang, S.R. Liu, C.Q. Xiao, et al. Corrosion resistance of 15-15Ti and 316Ti austenitic steels as fuel cladding in liquid lead-bismuth eutectic at 550 ℃ : the dominant role of grain structure. Corros. Sci., 2023, 218: 111169.

D. Wang, A. Leong, W.Q Zhuo, et al. Aluminum alloy corrosion and precipitation in high temperature flow loop simulating environment after loss of coolant accidents. J. Alloys Compd., 2022, 896: 16305.

D. Wang, A. Leong, Q.F. Yang, et al. Corrosion behavior of aluminum alloy in simulated nuclear accident environments regarding the chemical effects in GSI-191. Nucl. Eng. Technol., 2022, 54(11): 4062-4071.

D. Wang, R.X. Liang, F.L. Niu, et al. The accumulation and flow resistance characteristics of LOCA-generated debris in different PWR fuel assemblies. Ann. Nucl. Energy, 2022, 173, 109100.

D. Wang, B.C. Chang, T.Y. Zhang, et al. Evaluation of chemical effects on fuel assembly blockage following a loss of coolant accident in Nuclear Power Plants. Int. J. Energy Res., 2020, 4, 5488-5499.

D. Wang, F.L. Niu, R.X. Liang, et al. Assessment of head loss through LOCA-generated debris deposited in PWR fuel assemblies. Ann. Nucl. Energy., 2020, 137: 107037.

专利成果

牛风雷，王达，郭张鹏，等.模拟碎片对燃料组件压降影响的装置及冷段破口模拟方法，中国发明专利，ZL 2018 1 0554713.0.

郝祖龙，王达，刘祥，等. 一种液态金属锂物性参数测试系统及其测试方法，中国发明专利，ZL 2020 1 0074268.5.

学术报告

D. Wang, F.L. Niu, W.Q. Zhuo, et al. Accumulation and head-loss characteristics of LOCA-generated debris in a fuel assembly [C]. Proceeding of the 27th International Conference on Nuclear Engineering, May 19-24, 2019, Ibaraki, Japan.

D. Wang, F.L. Niu, W.Q. Zhuo, et al. Experimental study of debris-loading head loss test for PWR fuel assembly after LOCA [C]. Proceeding of the 25th International Conference on Nuclear Engineering, July 2-6, 2017, Shanghai, China.

王达，牛风雷，郝鹏飞，等. 微纳米结构表面强化沸腾传热研究, 2015年核反应堆系统设计技术重点实验室学术年会，成都，中国

获得荣誉

2023年首届中国核工业教育学会优秀博士学位论文二等奖