面向等离子体壁材料的腐蚀行为与涂层防护综述

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、B...

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

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 of solid plasma wall materials and the main characteristics of common PFMs, indicating that wall evaporation and sputtering under the action of hot plasma are the main corrosion behaviors of wall materials, and the structural defects caused by particle irradiation will increase the dissolution and diffusion of hydrogen isotopes in the wall material, deposited on the surface of the wall material along with impurities. Then, the paper focuses on the Chinese and international researches about the corrosion degree caused by the evaporation and sputtering of carbon wall, tungsten wall and beryllium wall materials under the action of plasma and the chemical corrosion principle of hydrocarbon combination, and the latest research progress of carbon-based composite materials, tungsten-based composite materials and stainless steel protective coating plasma wall materials developed on this basis, and the comparison shows that high-Z alloyed protective coatings and preparation technologies have huge application prospects. Finally, the paper analyzes some of the key basic problems that have to be solved in the current development of heat-resistant corrosion and good plasma compatibility wall materials, and proposes the main technical directions and development trends of PFMs in the future. It is expected to provide an important reference for the research and development of new protective coating materials used in extreme conditions of fusion reactors.