背景:
阅读

周海山


周海山

基本信息:

男,博士,聚变堆材料及部件研究室室务委员,中科院青年创新促进会会员,负责材料与氢同位素方向研究。任“十三五”国家重大科技基础设施CRAFT项目“偏滤器等离子体与材料相互作用研究平台”一级课题负责人,等离子体所“先进材料与氚”方向工作组协调人。在国际期刊上发表论文40余篇, 申请发明专利多项。

教育背景:
The Graduate University for Advanced Studies (NIFS) 聚变工程学 博士
中国科学院研究生院 等离子体物理 硕士
华中科技大学 机械设计制造及其自动化 学士

研究方向:
氢同位素与材料相互作用;
等离子体装置研发;

近五年论文发表情况:
[1] Lu Wang, Hai-Shan Zhou* et al., Studies on accelerated hydrogen isotopes permeation through plasma-facing components of fusion reactors, Phys. Scripta T171 (2020) 014032.
[2] Hao-Dong Liu, Hai-Shan Zhou* et al., The major trap sites of deuterium in CuCrZr alloy, Nucl. Mater. Energy 23 (2020) 100755.
[3] Hai-Shan Zhou et al., A tritium permeation 'short cut' for plasma-facing components of fusion reactors, Nucl. Fusion 59(1) (2019) 014003.
[4] Hao-Dong Liu, Hai-Shan Zhou*, Deuterium plasma driven permeation behavior in a Chinese reduced activation martensitic/ferritic steel CLF-1, J. Nucl. Mater. 514 (2019) 109.
[5] H.-S. Zhou et al., Reexamination of D retention behavior in He ion irradiated RAFMs, Nucl. Fusion 58 (2018) 056017.
[6] Hao-Dong Liu, Hai-Shan Zhou* et al., A Study on Deuterium Retention Behavior of Plasma-Facing Materials for EAST, IEEE Trans. Plasma Sci. 46 (2018) 2198.
[7] Hai-Shan Zhou et al., Deuterium permeation and retention in copper alloys, J. Nucl. Mater. 493 (2017) 398.
[8] Yu-Ping Xu,..., H. Zhou* et al., Plasma exposure behavior of re-deposited tungsten on structural materials of fusion reactors, J. Nucl. Mater. 488 (2017) 129.
[9] Hai-Shan Zhou et al., Deuterium retention in molten salt electrodeposition tungsten coatings, Fusion Eng. Des. 113 (2016) 265.
[10] F. Liu, H. Zhou* et al., Gas-driven permeation of deuterium through tungsten with different microstructures, Fusion Eng. Des. 113 (2016) 216.
[11] H. -S. Zhou et al., Surface condition effects on tritium permeation through the first wall of a water-cooled ceramic breeder blanket, Fusion Eng. Des. 109 (2016) 586.
[12] Yu-Ping Xu,..., H. Zhou* et al., Deuterium permeation behavior of HTUPS4 steel with thermaloxidation layer, Fusion Eng. Des. 113 (2016) 201.
[13] Yu-Ping Xu,..., H. Zhou* et al., Studies on oxidation and deuterium permeation behavior of a low temperature α-Al2O3-forming FeCrAl ferritic steel, J. Nucl. Mater. 477 (2016) 257.
[14] Yu-Ping Xu,..., H. Zhou* et al., Influence of He ions irradiation on the deuterium permeation and retention behavior in the CLF-1 steel, Nucl. Instr. Meth. B 388 (2016) 5.

近五年国际会议口头报告:
[1] Studies on Accelerated Hydrogen Isotopes Permeation through Plasma-Facing Components of Fusion Reactors, 17th International Conference on Plasma-Facing Materials and Components (PFMC-17), Eindhoven, the Netherlands, 2019.5.20-2019.5.24(邀请)
[2] D retention in high-energy he-ion irradiated rafm steel: surface and bulk damage effects, 18th International Conference on Fusion Reactor Materials (ICFRM-18), Aomori, Japan, 2017.11.5 - 2017.11.10 (邀请)
[3] The new plasma facing material test facility at ASIPP, CN-KO Workshop on W-based metal Wall/Divertor & Plasma-Wall Interaction, Jeju, Korea, 2020.1.11-2020.1.12 (口头)
[4] A Compact Linear Facility for Plasma Source Testing, 7th International Workshop on Plasma Material Interaction Facilities for Fusion (PMIF 2019), La Jolla, USA, 2019.10.22-2019.10.25 (口头)
[5] Hydrogen isotope permeation through the cooling tube from gaps between tungsten tiles of ITER-like PFCs 26th ITPA meeting on SOL/divertor physics, Madison, Wisconsin, USA, 2018.12.11-2018.12 (口头)
[6] Plasma driven permeation of D through a Chinese reduced activation martensitic/ferritic steel CLF-1, 14th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS2018), Knoxville, US, 2018.6.25 - 2018.6.27 (口头)
[7] D plasma-driven permeation through PFMCs, 6th International Workshop on Plasma Material Interaction Facilities for Fusion Research, Tsukuba, Japan, 2017.11.1 - 2017.11.3 (口头)
[8] Progress of W-relevant plasma-material interaction studies at ASIPP. Third Research Coordination Meeting on Plasma-wall Interaction with Irradiated Tungsten and Tungsten Alloys in Fusion Devices, Vienna, Austria, 2017.6.27-2017.6.30 (口头)
[9] Deuterium transport in copper alloys, 13th China-Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering (CJS-13), Hefei, China, 2016.9.26 - 2016.9.29 (口头)
[10] EAST contributors, Effects of Deposited Tungsten on the Plasma Exposure Behavior of Structural Materials, the 22nd Topical Meeting on the Technology of Fusion Energy (TOFE-22), Philadelphia, USA, 2016.8.22 - 2016.8.25 (口头)