姓名：周海山
地址：科学岛
类型：硕导
所在科研单元：等离子体所


导师介绍



论文发表情况（— 2018.06）：第一及通讯作者[1] H.-S. Zhou et al., Reexamination of D retention behavior in He ion irradiated RAFMs, Nucl. Fusion 58 (2018) 056017.[2] 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.[3] Hai-Shan Zhou et al., Deuterium permeation and retention in copper alloys, J. Nucl. Mater. 493 (2017) 398.[4] 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.[5] Hai-Shan Zhou et al., Deuterium retention in molten salt electrodeposition tungsten coatings, Fusion Eng. Des. 113 (2016) 265. [6] F. Liu, H. Zhou* et al., Gas-driven permeation of deuterium through tungsten with different microstructures, Fusion Eng. Des. 113 (2016) 216. [7] 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.[8] Yu-Ping Xu,..., H. Zhou* et al., Deuterium permeation behavior of HTUPS4 steel with thermaloxidation layer, Fusion Eng. Des. 113 (2016) 201.[9] 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.[10] 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.[11] H. Zhou* et al., Effects of surface conditions on the plasma-driven permeation behavior through a ferritic steel alloy observed in VEHICLE-1 and QUEST, J. Nucl. Mater. 463 (2015) 1066.[12] H. Zhou* et al., Bi-Directional Hydrogen Isotopes Permeation through the First Wall of a Magnetic Fusion Power Reactor, J. Plasma Fusion Res. SERIES 11 (2015) 10.[13] F. Liu,..., H. Zhou* et al., Defect production and deuterium retention in quasi-homogeneously damaged tungsten, Nucl. Instr. Meth. B 351 (2015) 23.[14] H. Zhou* et al., Gas- and plasma-driven hydrogen permeation through a reduced activation ferritic steel alloy F82H, J. Nucl. Mater. 455 (2014) 470.[15] H. Zhou* et al., First Wall Particle Flux Measurements by an F82H Permeation Probe in QUEST, Plasma Fusion Res. 9 (2014) **.[16] H. Zhou* et al., Hydrogen plasma-driven permeation through a reduced activation steel alloy F82H, Fusion Sci. Technol. 63 (2013) 361.[17] H. Zhou* et al., Bi-Directional Hydrogen Permeation through F82H under DEMO-Relevant Conditions, Plasma Fusion Res. 8 (2013) **.[18] H.S. Zhou et al., Exposure of vacuum plasma spraying tungsten to PISCES and DIII-D plasmas, Fusion Eng. Des. 86 (2011) 325.

Introduction





研究领域



等离子体与材料相互作用氢同位素在材料中的行为实验装置研发

招生专业



学术硕士招生计划：          1、专业：材料物理与化学（硕士）招生方向：等离子体与材料相互作用专业学位硕士招生计划：          1、专业：材料与化工（专硕）招生方向：聚变堆材料的制备与应用工程管理硕士招生计划：          1、专业：工程管理（专硕）招生方向：大科学工程管理学术硕士招生计划：          1、专业：材料物理与化学（硕士）招生方向：等离子体与材料相互作用          2、专业：材料物理与化学（硕士）招生方向：聚变堆材料的制备与应用专业学位硕士招生计划：          1、专业：材料与化工（专硕）招生方向：等离子体与材料相互作用          2、专业：材料与化工（专硕）招生方向：聚变堆材料的制备与应用工程管理硕士招生计划：          1、专业：工程管理（专硕）招生方向：大科学工程管理          2、专业：工程管理（专硕）招生方向：核能工程管理学术硕士招生计划：          1、专业：材料物理与化学（硕士）招生方向：聚变堆材料的制备与应用专业学位硕士招生计划：          1、专业：材料与化工（专硕）招生方向：等离子体与材料相互作用          2、专业：材料与化工（专硕）招生方向：聚变堆材料的制备与应用工程管理硕士招生计划：          2、专业：工程管理（专硕）招生方向：核能工程管理

研究成果