期刊论文

Review on the Corrosion Behavior and Coating Protection of Plasma Facing Materials

中文

表面技术

1001-3660

2021

50

02

123-133

10.16490/j.cnki.issn.1001-3660.2021.02.013

国家重点研发计划（2017YFE0301300）~~；

本校为第一机构

面向等离子体材料（Plasma Facing Materials, PFMs）可保护磁约束核聚变装置部件,使此部件不受芯部边缘等离子体的影响,但等离子体与壁相互作用（Plasma-Wall Interactions, PWI）所引起的高温腐蚀、辐射损伤和燃料滞留等问题已然成为先进核聚变装置的发展瓶颈。目前,低Z材料（C、Be）掺杂元素合金化、高Z材料（W、Mo）掺杂元素合金化以及不锈钢防护涂层是面向等离子体壁材料缓解等离子体作用的首选防护涂层。阐述了固体等离子体壁材料的一般腐蚀机制和常见PFMs的主要特征,发现热流等离子体作用下的壁蒸发和溅射是造成壁材料腐蚀的主要原因,而粒子辐照带来的组织结构缺陷将增强氢同位素在壁材料...

Plasma facing materials(PFMs)are used to protect the components of magnetic confinement nuclear fusion devices from the plasma at the core edge,but 1the problems of high temperature corrosion,radiation damage and fuel retention of plasma-wall interactions(PWI)have become the development bottleneck of advanced nuclear fusion devices.The alloying of doped elements of both low-Z materials(C,Be)and high-Z materials(W,Mo),and stainless steel are currently the preferred protective coatings for plasma wall materials to relieve the effect of plasma.This paper describes the general corrosion mechanism ...