教师简介：
　姓　名： 徐跃
　职　称： 讲师
　职　务：

　所属系： 金属材料工程系
　邮　箱： xuyue**@163.com
　电　话：

个人简历：
2007.09-2011.07 合肥工业大学 金属材料工程 本科
2011.09-2014.07 中国科学院等离子体物理研究所 材料物理与化学 硕士
2014.10-2017.09 日本综合研究大学院大学 核融合科学研究所 核能科学与工程 博士


主要研究领域、方向：
1.运用直线等离子体装置开展材料辐照实验，研究等离子体与材料的相互作用。
2.低活化钢的氢同位素渗透滞留行为研究。
3.第一壁钨涂层对氢同位素渗透滞留行为的影响。


研究成果（代表性成果）：
1.测得氢同位素在低活化钢F82H (Fe-8Cr-2W)中的扩散参数，验证了同位素效应并在实验上证实了双向等离子体与气体驱动渗透低活化钢的现象。
2.测得氢同位素在物理溅射沉积钨涂层中的扩散参数，发现晶体缺陷会增大氢同位素滞留。
3.通过渗透膜法测定球型托卡马克QUEST（九州大学）第一壁入射氢粒子流。


目前承担科研项目:


获奖情况：
2014-2017 日本政府文部科学省奖学金
2016 Outstanding Poster Award
2010 国家奖学金，校一等奖学金
2009 校三等奖学金
2008 校单项奖学金

著作论文（代表作）：
1.Y. Xu, C. Xie, S. Qin et al., Preliminary R&D on flat-type W/Cu plasma-facing materials and components for Experimental Advanced Superconducting Tokamak, Physica Scripta T159 (2014) 014008.
2.Y. Xu, Y. Hirooka, T. Nagasaka, J. Yagi, Hydrogen Gas-driven Permeation through F82H Steel Coated with Vacuum Plasma-Sprayed Tungsten, Plasma and Fusion Research, 11 (2016) **.
3.Y. Xu, Y. Hirooka, T. Nagasaka, Bi-directional hydrogen isotopes permeation through a reduced activation ferritic steel F82H, Fusion Engineering and Design, DOI: 10.1016/j.fusengdes.2017.04.022 (2017).
4.Y. Xu, Y. Hirooka, T. Nagasaka, N. Ashikawa, Hydrogen Isotopes Plasma-Driven Permeation through Tungsten Coated Reduced Activation Ferritic Steel F82H, Plasma and Fusion Research, 12 (2017) **.
5.Y. Xu, Y. Hirooka, N. Ashikawa, T. Nagasaka, Hydrogen isotopes transport in sputter-deposited tungsten coatings, Fusion Engineering and Design, DOI: 10.1016/j.fusengdes.2017.07.021 (2017).
6.Y. Xu, A. Kuzmin, Y. Hirooka, K. Hanada and the QUEST group, Hydrogen Permeation through Sputter-Deposited Tungsten Coated F82H in QUEST, Plasma and Fusion Research, 12 (2017) **.
7.Y. Xu, Y. Hirooka, N. Ashikawa, T. Nagasaka, Hydrogen isotopes plasma-driven permeation through sputter-deposited tungsten coated F82H, IEEE Transactions on Plasma Science, under review (2017).
8.H. Bi, Y. Hirooka, J, Yagi, Y. Xu, A study on hydrogen transport in a liquid metal GaInSn by plasma-driven permeation method, Nuclear Materials and Energy, under review (2017).
9.W. Wang, Q. Li, S. Zhao, Y. Xu, et al., Application of e-beam welding in W/Cu divertor project for EAST, Fusion Engineering and Design, 98 (2015) 1415-1418.
10.W. Wang, Q. Li, S. Zhao, S. Chang, Y. Xu, et al., Non-destructive Testing of EAST W/Cu Divertor Components, Fusion Science and Technology 66 (2014) 125-130.
11.S. X. Zhao, Q. Li, W. J. Wang, C. Li, D. D. Zhang, R. Wei, S. G. Qin, Y. L. Shi, L. J. Peng, N. J. Pan, Y. Xu, G. H. Liu, et al., Influence of Interfacial Oxidation on the High-Heat-Flux Performance of HIP-Manufactured Flat-Type W/Cu Plasma-Facing Components for EAST, Fusion Science and Technology 67 (2015) 784-791.