华北电力大学核科学与工程学院副教授；北京航空航天大学物理学院“凝聚态物理”博士学位。

工作经历

(1) 2018-09 至 2020-08, 深圳大学李建刚院士工作站

研究方向

聚变堆壁材料的氢氦等离子体辐照效应；

利用重离子在材料内部预置晶格缺陷，模拟研究中子辐照对钨基壁材料中氢同位素滞留行为的影响效应。

教学课程

校通选课：《百年电力·核能发电篇》

核专业课：《核电厂材料》《核电专业英语》

校选修课：《可控核聚变的寻梦之旅》

近五年主持/参加的国家自然科学基金项目/课题

(1) 国家自然科学基金委员会, 面上项目,重离子与氦等离子体辐照协同效应对钨中氘滞留行为的影响研究, 在研, 参与

(2) 国家自然科学基金委员会, 青年科学基金项目,预置离位损伤对钨中氘滞留与起泡行为规律的影响研究, 结题, 主持

近五年主持/参加的其他科研项目/课题

(1) 中国国际核聚变能源计划执行中心, 国家磁约束核聚变能发展研究专项,氢同位素渗透动态测量的近端探针热脱附技术, 在研, 参与

(2) 北京市自然科学基金委, 面上项目,面向等离子体材料氢同位素滞留的非恒温效应研究, 在研, 主持

(3) 中国博士后科学基金会, 面上项目,辐照温度不稳定情况下的钨中氘滞留与起泡行为研究, 结题, 主持

获得荣誉

（1）第一作论文Nucl. Fusion, 2016, 56(3) 036010获得“中国区Top Cited Author Award”；

（2）深圳大学李建刚院士工作站“优秀博士后”。

代表性学术论文

[1] X.-L. Zhu, Y. Zhang, L. Cheng, Y. Yuan, G. De Temmerman, B.-Y. Wang, X.-Z. Cao, G.-H. Lu*, Deuterium occupation of vacancy-type defects in argon-damaged tungsten exposed to high flux and low energy deuterium plasma, Nuclear Fusion 56(3) (2016) 036010.

[2] X.-L. Zhu, L. Cheng, G. De Temmerman, L.Q. Shi, Y. Yuan, B.Y. Wang, X.Z. Cao, E.Y. Lu, Y. Zhang, G.H. Lu, Effects of stress-relief pre-annealing on deuterium trapping and diffusion in tungsten, Fusion Engineering and Design 125 (2017) 526-530.

[3] X.-L. Zhu, Y. Zhang, L. Cheng, L.-Q. Shi, G. De Temmerman, Y. Yuan, H.-P. Liu, G.-H. Lu, Suppression of deuterium-induced blistering in pre-damaged tungsten exposed to short-duration deuterium plasma, Journal of Nuclear Materials 500 (2018) 295-300.

[4] X.-L. Zhu, Y. Zhang, A. Kreter, L.-Q. Shi, Y. Yuan, L. Cheng, C. Linsmeier, G.-H. Lu, Aggravated blistering and increased deuterium retention in iron-damaged tungsten after exposure to deuterium plasma with various surface temperatures, Nuclear Fusion 58(10) (2018) 106005.

[5] S. Wang, X.-L. Zhu, L. Cheng, W. Guo, M. Liu, C. Xu, Y. Yuan, E. Fu, X.-Z. Cao, G.-H. Lu, Effect of heavy ion pre-irradiation on blistering and deuterium retention in tungsten exposed to high-fluence deuterium plasma, Journal of Nuclear Materials 508 (2018) 395-402.

[6] X.L. Zhu, L. Cheng, S.W. Wang, Y. Yuan, G.H. Lu, Y. Zhang, E.Y. Lu, X.Z. Cao, J.J. Huang, Reduced blister quantity in damaged tungsten exposed to deuterium plasma, Science China-Physics Mechanics & Astronomy 62(5) (2019) 957021.

[7] T. Wang, Y. Yuan, W. Guo, X. Ma, M. Liu, J. Wang, L. Cheng, X.-L. Zhu*, G.-H. Lu, Deuterium behavior in tungsten exposed to deuterium plasma with rising or declining temperature, Journal of Nuclear Materials 537 (2020) 152243.

[8] S. Wang, W. Guo, Y. Yuan, N. Gao, X.-L. Zhu, L. Cheng, X. Cao, E. Fu, L. Shi, F. Gao, G.-H. Lu, Evolution of vacancy defects in heavy ion irradiated tungsten exposed to helium plasma, Journal of Nuclear Materials 532 (2020).

[9] Wang, Z., Gao, L., Zhu, X.-L., Yuan, Y., Wang, S., Cheng, L., & Lu, G.-H. Effect of rhenium on defects evolution behavior in tungsten under irradiation. Nuclear Fusion 61(3) (2021).

[10] S. Wang, W. Guo, L. Cheng, T. Schwarz-Selinger, M. Liu, X.-L. Zhu, Y. Yuan, E. Fu, Lu, G.-H. (2021). Dependence of blistering and deuterium retention on damage depth in damaged tungsten exposed to deuterium plasma. Nuclear Fusion 61(5) (2021) 056003.

[11] Xiu-Li Zhu; Zhen-Hua Ke; Long Cheng; Yue Yuan; Ying Zhang; Zheng Wang; Guang-Hong Lu; The effect of pre-damage distribution on deuterium-induced blistering and retention in Tungsten, Fusion Engineering and Design, 2023, 189(113494)

[12] Xiu-Li Zhu; Zhen-Hua Ke; Long Cheng; Peng Zhang; Yue Yuan; Xing-Zhong Cao; Guang-Hong Lu; The effect of High-Temperature Pre-Damage on Vacancy-Type defects and deuterium retention in tungsten, Nuclear Materials and Energy, 2024, 38(101620)

联系邮箱

zhuxiuli@ncepu.edu.cn