
贺秀杰 副教授
办公电话:07563668839
电子邮箱:hexiujie@mail.sysu.edu.cn
研究领域:轻水堆事故容错燃料(ATF)包壳涂层的制备及性能表征; 核材料在铅铋堆中的腐蚀行为研究
学科方向
核燃料循环与材料
个人简介
贺秀杰,男,汉族,1987年10月生,山东济宁人,中共党员,理学博士,中山大学“百人计划”副教授、博士生导师
主要研究方向:涂层的制备与表征
电子邮箱:hexiujie@mail.sysu.edu.cn
联系地址:广东省珠海市唐家湾镇中山大学珠海校区2号学院楼C区520室
研究领域
1. 轻水堆事故容错燃料(ATF)包壳涂层的制备及性能表征
2. 涂层在铅铋堆中的腐蚀行为研究
工作经历
2025.3.1 — 2027.2.28,国家自然科学基金委借调,办公室(科研诚信建设办公室)学风建设处,流动编制业务主管
2016.08 — 至今,中山大学,中法核工程与技术学院,“百人计划”副教授、博士生导师
2014.07 — 2016.07,清华大学,核研院反应堆结构研究室(104室),博士后(助理研究员)
教育背景
2011.05 — 2014.07,中国科学院上海应用物理研究所(联合培养),核技术及应用,博士
2009.09 — 2014.07,山东大学,凝聚态物理,理学博士(硕博连读)
2005.09 — 2009.07,曲阜师范大学,物理学,理学学士
科研项目
20. 季华实验室,横向项目,涂层制备及理化性能测试,2024/01-2024/04,8万元
19. 南京海通电子材料科技有限公司,横向项目,取样器及驱动线表面防铅铋粘附涂层制备,2023/12-2024/06,10万元
18. 兰州宏祥电力技术开发有限责任公司,横向项目,316L不锈钢表面涂层制备及性能测试,2023/12-2024/06,10万元
17. 核工业西南物理研究院,横向项目,滤波薄膜,2023/05/01-2023/05/31,19.43万元
16. 广东省自然科学基金,面上项目,Cr/Cr-N纳米叠层涂层辐照与腐蚀的协同损伤机制研究,2023/01-2025/12,10万元
15. 国家自然科学基金委员会,面上项目,耐事故包壳Cr/Cr-N纳米叠层涂层的制备及其辐照效应研究,2023/01—2026/12,55万元
14. 中国***研究设计院,GFJG项目,铅铋环境下***研究,2022/08—2024/06,181万元
13. 珠海市,产学研合作及基础与应用基础研究项目,事故容错燃料包壳Cr/Cr-N纳米叠层涂层的制备及性能研究,2022/01—2023/12,10万元
12. 中广核研究院有限公司,横向项目,金属表面防铅铋粘附涂层研究,2021/09—2022/03,28万元
11. 广州市科技计划项目,基础与应用基础研究项目(博士青年科技人员类),事故容错燃料包壳CrSiN复合涂层的制备及其氧化性能和机械性能的研究,2021/04—2023/03,5万元
10. 安徽伯华氢能源科技有限公司,横向项目,反应堆中氢气在线监测技术研发,2020/08—2021/05,3万元
9. 东莞市典雅五金制品有限公司,横向项目,金属材料表面耐磨损涂层的多弧离子镀沉积工艺开发,2020/01—2020/12,50万元
8. 教育部,高校基本科研业务费中山大学青年教师培育项目,19lgpy299,事故容错燃料包壳涂层的机械性能研究,2019/01—2021/12,15万元
7. 中国***研究院,GFJG项目,***样品研发,2019/10—2019/11,9万元
6. 安徽伯华氢能源科技有限公司,横向项目,反应堆中氢气在线监测技术研发,2019/07—2019/12,3万元
5. 清华大学核能与新能源技术研究院反应堆结构研究室,横向项目,高温气冷堆堆内构件材料辐照特性调研及安全评价分析,2019/01—2019/12,5万元
4. 中国***研究院,横向项目,***材料在***中的应用调研,2017/12/1—2017/12/31,3万元
3. 中山大学,百人计划紧缺人才科研启动费,2016/08—2019/08,30万元
2. 国家自然科学基金委员会,青年项目,11502130,高温气冷堆金属堆内构件散体结构的抗震性能研究,2016/01—2018/12,20万元
1. 中国博士后科学基金会,面上二等资助,2015M571052,高温气冷堆金属堆内构件散体结构的动力学分析方法研究,2014/07—2016/07,5万元
学术论文
32. Zihao Wang, Yanxu Huang, Yunyu Qiu, Zhijiong Wang, Yuxin Tang, Yih-Min Wang, Hung-Chun Li, Kai Wang*, Xiujie He*, Progresses in nucleate boiling studies and gaps between experimental works and real-world applications in in-vessel retention (IVR), Ann. Nucl. Energy 225 (2026) 111786.
31. Jiaojiao Ma, Lili Xing, Jie Tan, Hui Wang, Xiujie He*, Xing Yin*, Temperature-dependent degradation of Al2O3—CrAl-O—Cr-O—Al-O multilayer coatings on ferritic-martensitic steels in oxygen-saturated lead–bismuth eutectic, Mater. Des. 254 (2025) 114101.
30. Zheng Qu, Yaoping Xie, Jiaojiao Ma, Chuiyi Meng, Hui Wang*, Xiujie He*, Unveiling the dual role of ion irradiation on the corrosion behavior of lean-Cr FeCrAl alloys in a simulated PWR environment, Corros. Sci. 237 (2024) 112344.
29. Tianhao Zhang, Jiaojiao Ma, Weizheng Liu, Chuiyi Meng, Wei Qi*, Hui Wang, Xiujie He*, Corrosion behavior of Al-O coating in oxygen-saturated lead-bismuth eutectic at 550 ◦C, J. Mater. Res. Technol. 30 (2024) 4123.
28. Chuiyi Meng, Jiaojiao Ma, Hui Wang, Wenguan Liu, Yong Hu, Baoliang Zhang, Menghe Tu, Cenxi Yuan*, Xiujie He*, Enhancing the oxidation behaviors of Zr alloys for nuclear fuel cladding using nanolamellar Cr/CrN coating, Corros. Sci. 227 (2024) 111725.
27. Chuiyi Meng, Jishen Jiang, Jiaojiao Ma, Tianhao Zhang, Weizheng Liu, Peng Xie, Hui Wang, Xianfeng Ma*, Xiujie He*, Improving the high-temperature oxidation resistance of CrN coating by gradient deposition considering internal stress effects, Nucl. Mater. Energy, 37 (2023) 101531.
26. Shuang Yang, Run-Jie Fang, Guo Yang*, Li-Jun Lv, Xing-Bo Han*, Wei Liu, Xiu-Jie He*, Peng-Fei Zhu, Influence of element substitutions on poisoning behavior of ZrV2 alloy: theoretical and experimental investigations, Nucl. Sci. Technol. 34 (2023) 113.
25. Zheng Qu, Chuiyi Meng, Juncheng Huang, Yuchang Mei, Yinmeng Zhang, Jiaojiao Ma, Wenguan Liu, Hui Wang*, Xiujie He*, Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment, Mater. Des. 230 (2023) 111948.
24. Jiaojiao Ma, Jie Tan*, Yue Zhou, Chuiyi Meng, Hui Wang, Weiqi Yang, Xiujie He*, Influence of a Mo interlayer on the oxidation behavior of a Cr coating on a Zr alloy substrate, Corros. Sci. 218 (2023) 111192.
23. Hui Wang, Gengyu Liang, Chuiyi Meng, Xuguang An, Yuan Wang*, Xiujie He*,A comparative study on the corrosion performance of four FeCrAl alloys with different Cr contents in contact with oxygen-saturated LBE, J. Mater. Res. Technol. 23 (2023) 3492.
22. Zheng Qu, Guixiao Shang, Siyuan Ma, Chuiyi Meng, Peng Xie, Hui Wang, Xuguang An, Xiujie He*, Friction and Wear Properties of Cr-Nx Coatings for Nuclear Fuel Cladding, Coatings, 12 (2022) 163.
21. Lijun Lv, Jian Lin, Guo Yang, Zhaowei Ma, Linhua Xu, Xiujie He*, Xingbo Han, Wei Liu, Hydrogen storage performance of LaNi3.95Al0.75Co0.3 alloy with different preparation methods, Progr. Nat. Sci.: Mater. Int. 32 (2022) 206.
20. Ji-Shen Jiang, Dong-Qing Wang, Ming-Yue Du, Xian-Feng Ma*, Chen-Xue Wang, Xiu-Jie He*, Interdiffusion behavior between Cr and Zr and its effect on the microcracking behavior in the Cr-coated Zr-4 alloy, Nucl. Sci. Tech. 32 (2021) 134.
19. Jiaojiao Ma, Chuiyi Meng, Hui Wang, Xiujie He*, Effect of Al Content on the High-Temperature Oxidation Resistance and Structure of CrAl Coatings, Coatings, 11 (2021) 1434.
18. Xinfeng Li, Chuiyi Meng, Xiantao Xu, Xiujie He*, Canyu Wang, Effect of Al content on high-temperature oxidation behavior and failure mechanism of CrAl-coated Zircaloy, Corros. Sci., 192 (2021) 109856.
17. Biao Ma, Bin Luo, Zhuozheng Wang, Chuiyi Meng, Xiujie He*, Friction and wear properties of CrAl-based coatings for nuclear fuel cladding, Front. Energy Res., 9 (2021) 622708.
16. Xiujie He, Shengzhi Yang, Lanlan Huang, Chuiyi Meng, Yuan Wang, Jie Tan, Friction and wear properties of CrSi-based coatings for nuclear fuel cladding, Surf. Coat. Technol. 402 (2020) 126311.
15. Min Liu, Wenguan Liu, Xiujie He*, Yantao Gao*, Renduo Liu, Xingtai Zhou, Defects evolution and element segregation of Ni-Mo-Cr alloy irradiated by 30 keV Ar ions, Nucl. Eng. Technol. 52 (2020) 1749.
14. Sheng-Li Chen, Xiu-Jie He*, Cen-Xi Yuan*, Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors, Nucl. Sci. Tech. 31 (2020) 32.
13. Xiujie He, Hanyu Zhan, Jian Lin, Gengyu Liang, Shengzhi Yang, Chuiyi Meng, Xianfeng Ma, Jie Tan*, Min Liu*, Effect of Si content of CrSi-based coatings on their oxidation resistance in high temperature air, Ceram. Int. 46 (2020) 11357.
12. Xiujie He, Zhonghe Tian, Bohao Shi, Xiantao Xu, Chuiyi Meng, Weian Dang, Jie Tan*, Xianfeng Ma*, Effect of gas pressure and bias potential on oxidation resistance of Cr coatings, Ann. Nucl. Energy 132 (2019) 243.
11. Chuiyi Meng, Liu Yang, Yawen Wu, Jie Tan, Weian Dang, Xiujie He*, Xianfeng Ma*, Study of the oxidation behavior of CrN coating on Zr alloy in air, J. Nucl. Mater. 515 (2019) 369.
10. Xian-Feng Ma, Ya-Wen Wu, Jie Tan, Chui-Yi Meng, Liu Yang, Wei-An Dang, Xiu-Jie He*. Evaluation of corrosion and oxidation behaviors of TiAlCrN coatings for nuclear fuel cladding, Surf. Coat. Technol. 358 (2018) 521.
9. Xiujie He, Li Shi, Haiyan Li, Jie Tan, Baoliang Zhang, Alex Fok, Xinxin Wu, Libin Sun*, Experimental study to estimate the surface wear of nuclear graphite in HTR-PM, Ann. Nucl. Energy 116 (2018) 296.
8. Tan Jie, Zhang Xiaoming, Liu Wenguan, He Xiujie*; Zhao Mingwen*. Strain-Induced Tunable Negative Differential Resistance in Triangle Graphene Spirals, Nanotechnology, 29 (2018) 205202.
7. Xiujie He*,Jie Tan. Localized defects related to the 14N+ ion irrradiation-induced magnetism in SiC,Physica E 93 (2017) 6.
6. Xiujie He, Jinliang Song*, Jie Tan, Baoliang Zhang, Huihao Xia*, Zhoutong He, Xingtai Zhou, Mingwen Zhao*, Xiangdong Liu, Li Xu, Shuo Bai, SiC coating: an alternative for the protection of nuclear graphite from liquid fluoride salt, J. Nucl. Mater. 448 (2014) 1.
5. Xiujie He, Jinliang Song*, Huihao Xia*, Jie Tan, Baoliang Zhang, Zhoutong He, Xingtai Zhou, Zhiyong Zhu, Mingwen Zhao*, Xiangdong Liu, Li Xu, Shuo Bai, Direct characterization of ion implanted pyrolytic carbon coatings deposited from natural gas, Carbon 68 (2014) 95.
4. Xiujie He, Jie Tan, Baoliang Zhang, Mingwen Zhao*, Huihao Xia*, Xiangdong Liu, Zhoutong He, Xinmei Yang, Xingtai Zhou, Irradiation-induced magnetic ordering in SiC: experimental results and a density functional study, Appl. Phys. Lett. 103 (2013) 262409.
3. Xiujie He, Jinliang Song*, Li Xu, Jie Tan, Huihao Xia*, Baoliang Zhang, Zhoutong He, Lina Gao, Xingtai Zhou, Mingwen Zhao*, Zhiyong Zhu, Shuo Bai, Protection of nuclear graphite toward liquid fluoride salt by isotropic pyrolytic carbon coating, J. Nucl. Mater. 442 (2013) 306.
2. HE XiuJie, TAN Jie, BU HongXia, ZHANG HongYu, ZHAO MingWen*, The role of π electrons in the electronic structures and optical properties of graphyne, Chin. Sci. Bull. 57 (2012) 3080.
1. Xiujie He, Tao He, Zhenhai Wang, Mingwen Zhao*, Neutral vacancy-defect-induced magnetism in SiC monolayer, Physica E 42 (2010) 2451.
教学项目
3. 教学质量工程建设项目-教材建设-耐事故燃料包壳涂层的制备及性能表征,2023, 5万元
2. 质量工程项目-本科教学改革研究项目-《核物理介绍》教学中构建学生自主学习激励机制的探索性研究,2019/01-2020/12,2万元
1. 中山大学研究生课程建设项目,《核材料学(反应堆部分)》优质示范课程建设,2018/01-2018/12,3万元
教学论文
2. 贺秀杰,谭捷,袁岑溪,郭琛琛,《核物理介绍》教学中构建学生自主学习激励机制的探索性研究,教育教学论坛,2020, 11, 272-273.
1. 贺秀杰,谭捷,马显锋,杨卫岐,弹幕在研究生一年级《英文文献阅读》课堂教学中的应用探索,教育教学论坛,2019, 13, 172-174.
讲授课程
本科生课程
1. 核物理介绍(MN4),2017—至今
2. 分析化学、热力学、电化学实验课(CP4-TP),2019—至今
3. 化工单元操作(CP6-TD),2019
4. 化学实验III,2023
5. 大学物理实验,2022
6. 毕业论文,2022—2024
7. 核物理与核数据介绍,2023—至今
8. 普通化学与放射化学实验,2024
9. 金属工艺实训,2024—至今
硕士生课程
1. 核材料学(反应堆部分,INP8-TD),2017—至今
2. 燃料材料、化学及制备(CM2-TD),2017—至今
3. 辐射探测(CEA16-TP),2019
4. 全范围仿真机的实践教学,2019
5. 核燃料与核材料,2021
6. 先进核燃料与材料,2022
博士生课程
1. 核材料,2019
2. 核燃料与核材料,2021
3. 先进核燃料与材料,2022