偏滤器用钨基材料的热负荷损伤行为研究进展

罗来马, 陈宇, 姚刚, 朱晓勇, 朱大焕, 吴玉程

Research Progress on Heat Load Damage Behavior of Tungsten-Based Materials for Divertor

LUO Laima, CHEN Yu, YAO Gang, ZHU Xiaoyong, ZHU Dahuan, WU Yucheng

图1 磁约束核聚变托卡马克(Tokamak)偏滤器结构设计示意图[2,3]及其热负荷加载场景[13,26]

Fig.1 Schematics of magnetic confinement nuclear fusion Tokamak international thermonuclear experimental reactor (ITER)[2] (a) and divertor structure design[3] (b); and synergistic multi-field coupling loading scenarios of plasma-facing materials (PFMs) in future thermonuclear fusion reactors[13] (DEMO—demonstration plant, ELM—edge localized mode, VED—vertical displacement) (c) and sketch maps showing the general mechanism of crack formation in heat load tests[26] (d1, d2)