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朱秀丽

华北电力大学核科学与工程学院讲师。

北京航空航天大学物理学院凝聚态物理博士学位,安徽工业大学材料科学与工程学院材料科学与工程学士学位。

工作经历

w 2018.09-2.20.08 深圳大学李建刚院士工作站博士后

研究方向

w 聚变堆钨基壁材料的氢等离子体辐照效应研究;

w 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。

代表性科研项目

w 作为项目负责人,主持国家自然科学基金青年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【在研】;

w 作为项目负责人,主持中央高校中央高校基本科研业务专项资助项目聚变堆壁材料钨与氘等离子体相互作用的温度效应研究

w 作为项目负责人,主持中国博士后科学基金面上资助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【已结题】;

w 参与国家自然科学基金面上基金重离子与氦等离子体协同辐照效应对钨中氘滞留行为的影响研究【在研】;

w 参与科技部ITER专项壁材料等离子体辐照实验研究【已结题】。

获得荣誉

w 以第一作者发表的文章(代表性学术论文[1])获得中国区Top Cited Author Award

w 深圳大学李建刚院士工作站优秀博士后

发表学术论文

[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.

联系方式

邮箱地址:zhuxiuli@ncepu.edu.cn

欢迎对核材料辐照效应等相关领域感兴趣的同学来咨询。

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