报告时间：2026年3月27日（星期五）10:00
报告地点：材料楼601室
报 告 人：高亮 博士
工作单位：德国亥姆霍兹国家研究中心联合会于利希研究中心等离子体物理所
举办单位：材料科学与工程学院
报告简介：
Magnetic confinement fusion devices such as the TOKAMAK rely on sustaining a high-temperature plasma in close proximity to material surfaces that define and protect the reactor boundary. The interaction between the confined plasma and these plasma-facing materials—commonly referred to as plasma–surface interaction (PSI)—is a central challenge for achieving reliable and long-lived fusion operation. In a tokamak environment, energetic particles, heat fluxes, and radiation from the plasma continuously bombard the first wall and divertor components, leading to complex physical and chemical processes at the interface between plasma and solid surfaces.
Fundamentally, PSI encompasses several coupled mechanisms. Charged particles and neutrals from the edge plasma impact material surfaces, producing processes such as sputtering, reflection, implantation, and defect generation in the near-surface region. These processes modify both the plasma and the material: surface erosion introduces impurities back into the plasma, while implanted hydrogen isotopes accumulate in the material lattice. Such hydrogen isotope retention is particularly important because the fuel of fusion plasmas typically involves deuterium and tritium. Excessive retention can influence fuel inventory, safety considerations, and the overall efficiency of reactor operation.
Surface morphology and material composition evolve dynamically under sustained plasma exposure. Re-deposition of eroded material, formation of nanostructures, and radiation-induced defects can alter the thermal and mechanical properties of plasma-facing components. These changes feed back to the plasma boundary conditions, influencing recycling, edge plasma density, and power exhaust.
Understanding PSI therefore requires an interdisciplinary framework combining plasma physics, surface science, and materials science. Experimental investigations in tokamak devices and dedicated plasma exposure facilities, together with theoretical modeling and simulations, are used to clarify the underlying mechanisms and to guide the development of resilient plasma-facing materials. A fundamental grasp of plasma–surface interaction processes is essential for the design of next-generation fusion reactors and for achieving stable, efficient, and safe fusion energy production. An introductory talk will be presented: I will start from the basic concepts of nuclear fusion and then move forward into the relevant PSI processes. Three major issues toward a commercial TOKAMAK fusion reactor will be discussed taking ITER as an example.
报告人简介：
高亮，男，博士。自2010年在中科院等离子体物理研究所读博，2011年获得‘中科院-马普学会博士生联合培养计划’奖学金资助前往德国马普学会等离子体物理研究所深造，师从Christian Linsmeier教授并在Wolfgang Jacob资深研究员领导的研究小组继续从事聚变等离子体与材料表面相互作用PSI (Plasma-Surface Interaction)方向的实验研究。研究课题主要集中于聚变钨面向等离子体材料与氢同位素及氦等离子体相互作用，涉及氢、氘、氦等离子体辐照损伤及缺陷演化，以及这些元素在钨材料中的滞留、扩散及渗透行为研究。2015年博士毕业后继续在马普等离子体所从事博士后研究工作并于2017年获得欧洲聚变委员会（Eurofusion）青年研究员项目资助独立承担“聚变等离子体杂质对氢同位素滞留、扩散及渗透行为影响”。该项目每年在全欧盟范围内仅遴选5-10名新晋毕业博士进行为期两年约15-20万欧元的资助。2018年底项目结题后继续在IPP Garching从事博士后研究工作两年。2020年起至今就职于德国亥姆霍兹国家研究中心联合会于利希研究中心等离子体物理所，从事氢同位素及氦等轻质元素在核聚变材料内的行为研究，负责TDS实验室日常运作。至今已在德国从事高水平科学研究15年，其间指导博士研究生5名、硕士研究生8名。发表学术论文、专著40余篇，被引用900余次。其中以第一作者和通讯作者在国际核心期刊发表论文20篇，包括在Acta Materialia, Nuclear Fusion 等相关领域顶级期刊。多次参与聚变材料领域的重要国际会议进行学术交流，受邀在国际原子能机构IAEA Technical meeting on defect stabilization and hydrogen supersaturation (Aix en Provence, April, 2022)，面向等离子体材料与部件国际会议（International Conference on Plasma-Facing Materials and Components for Fusion Applications）, 聚变等离子体与表面相互作用（International Conference on Plasma-Surface Interactions in Controlled Fusion）等本领域重要国际会议做大会邀请报告，并以科研项目合作及讲座形式与国内多家科研院所一直保持紧密合作关系。
