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賀秀杰

賀秀杰副教授

辦公電話:18575665032(微信同號)

電子郵箱:hexiujie@mail.sysu.edu.cn

研究領域:輕水堆事故容錯燃料(ATF)包殼涂層的制備及性能表征; 核材料在鉛鉍堆中的腐蝕行為研究

學科方向

核燃料循環與材料

個人簡介

賀秀杰,男,漢族,1987年10月生,山東濟寧人,中共黨員,理學博士,中山大學“百人計劃”副教授、博士生導師

主要研究方向:涂層的制備與表征

聯系地址:廣東省珠海市唐家灣鎮中山大學珠海校區瀚林3號樓C區520室

研究領域

1. 輕水堆事故容錯燃料(ATF)包殼涂層的制備及性能表征

2. 涂層在鉛鉍堆中的腐蝕行為研究    

工作經歷                                                        

2025.3.1 — 2027.2.28,國家自然科學基金委借調,辦公室(科研誠信建設辦公室)學風建設處,流動編制業務主管

2016.08 — 至今,中山大學,中法核工程與技術學院,“百人計劃”副教授、博士生導師

2014.07 — 2016.07,清華大學,核研院反應堆結構研究室(104室),博士后(助理研究員)  

教育背景                                                     

2011.05 — 2014.07,中國科學院上海應用物理研究所(聯合培養),核技術及應用,博士

2009.09 — 2014.07,山東大學,凝聚態物理,理學博士(碩博連讀)

2005.09 — 2009.07,曲阜師范大學,物理學,理學學士

科研項目

21. 季華實驗室,橫向項目,固體涂層形貌及微觀結構表征,2025/09-2026/02,7.5萬元

20. 季華實驗室,橫向項目,涂層制備及理化性能測試,2024/01-2024/04,8萬元

19. 南京海通電子材料科技有限公司,橫向項目,取樣器及驅動線表面防鉛鉍粘附涂層制備,2023/12-2024/06,10萬元

18. 蘭州宏祥電力技術開發有限責任公司,橫向項目,316L不銹鋼表面涂層制備及性能測試,2023/12-2024/06,10萬元

17. 核工業西南物理研究院,橫向項目,濾波薄膜,2023/05/01-2023/05/31,19.43萬元

16. 廣東省自然科學基金,面上項目,Cr/Cr-N納米疊層涂層輻照與腐蝕的協同損傷機制研究,2023/01-2025/12,10萬元

15. 國家自然科學基金委員會,面上項目,耐事故包殼Cr/Cr-N納米疊層涂層的制備及其輻照效應研究,2023/01—2026/12,55萬元

14. 中國***研究設計院,GFJG項目,鉛鉍環境下***研究,2022/08—2024/06,181萬元

13. 珠海市,產學研合作及基礎與應用基礎研究項目,事故容錯燃料包殼Cr/Cr-N納米疊層涂層的制備及性能研究,2022/01—2023/12,10萬元

12. 中廣核研究院有限公司,橫向項目,金屬表面防鉛鉍粘附涂層研究,2021/09—2022/03,28萬元

11. 廣州市科技計劃項目,基礎與應用基礎研究項目(博士青年科技人員類),事故容錯燃料包殼CrSiN復合涂層的制備及其氧化性能和機械性能的研究,2021/04—2023/03,5萬元

10. 安徽伯華氫能源科技有限公司,橫向項目,反應堆中氫氣在線監測技術研發,2020/08—2021/05,3萬元

9. 東莞市典雅五金制品有限公司,橫向項目,金屬材料表面耐磨損涂層的多弧離子鍍沉積工藝開發,2020/01—2020/12,50萬元

8. 教育部,高校基本科研業務費中山大學青年教師培育項目,19lgpy299,事故容錯燃料包殼涂層的機械性能研究,2019/01—2021/12,15萬元

7. 中國***研究院,GFJG項目,***樣品研發,2019/10—2019/11,9萬元

6. 安徽伯華氫能源科技有限公司,橫向項目,反應堆中氫氣在線監測技術研發,2019/07—2019/12,3萬元

5. 清華大學核能與新能源技術研究院反應堆結構研究室,橫向項目,高溫氣冷堆堆內構件材料輻照特性調研及安全評價分析,2019/01—2019/12,5萬元

4. 中國***研究院,橫向項目,***材料在***中的應用調研,2017/12/1—2017/12/31,3萬元

3. 中山大學,百人計劃緊缺人才科研啟動費,2016/08—2019/08,30萬元

2. 國家自然科學基金委員會,青年項目,11502130,高溫氣冷堆金屬堆內構件散體結構的抗震性能研究,2016/01—2018/12,20萬元

1. 中國博士后科學基金會,面上二等資助,2015M571052,高溫氣冷堆金屬堆內構件散體結構的動力學分析方法研究,2014/07—2016/07,5萬元

學術論文 

34. Jiaojiao Ma, Jie Tan, Xing Yin, Hui Wang*, Xiujie He*, Effect of pre-irradiation on corrosion resistance of 9Cr1Si ferritic/martensitic steels in oxygen saturated-depleted stagnant lead-bismuth eutectic at 550 ?C, Corros. Sci. 260 (2026) 113540.

33. Wei Zhao, Qi Sun*, Zhihua Lu, Pengfei Yang, Xiujie He*, Minhao Zhu, Toward Understanding the formation and microstructure of complex multilayered oxide scales in flowing lead–bismuth eutectic (LBE), High Temp. Corros. Mater. 102 (2025) 34.

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*, In?uence 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.

 

教學項目

3. 教學質量工程建設項目-教材建設-耐事故燃料包殼涂層的制備及性能表征,2023, 5萬元

2. 質量工程項目-本科教學改革研究項目-《核物理介紹》教學中構建學生自主學習激勵機制的探索性研究,2019/01-2020/12,2萬元

1. 中山大學研究生課程建設項目,《核材料學(反應堆部分)》優質示范課程建設,2018/01-2018/12,3萬元

教學論文

2. 賀秀杰,譚捷,袁岑溪,郭琛琛,《核物理介紹》教學中構建學生自主學習激勵機制的探索性研究,教育教學論壇,2020, 11, 272-273.

1. 賀秀杰,譚捷,馬顯鋒,楊衛岐,彈幕在研究生一年級《英文文獻閱讀》課堂教學中的應用探索,教育教學論壇,2019, 13, 172-174.

講授課程

本科生課程

1. 核物理介紹(MN4),2017—至今

2. 分析化學、熱力學、電化學實驗課(CP4-TP),2019—至今

3. 化工單元操作(CP6-TD),2019

4. 化學實驗III,2023

5. 大學物理實驗,2022

6. 畢業論文,2022—2024

7. 核物理與核數據介紹,2023—至今

8. 普通化學與放射化學實驗,2024

9. 金屬工藝實訓,2024—至今

碩士生課程

1. 核材料學(反應堆部分,INP8-TD),2017—至今

2. 燃料材料、化學及制備(CM2-TD),2017—至今

3. 輻射探測(CEA16-TP),2019

4. 全范圍仿真機的實踐教學,2019

5. 核燃料與核材料,2021

6. 先進核燃料與材料,2022

博士生課程

1. 核材料,2019

2. 核燃料與核材料,2021

3. 先進核燃料與材料,2022