Recent Advances on Interface Design and Preparation of Advanced Tungsten Materials for Plasma Facing Materials

被引：4

作者：

Wu, Xuebang ^{[1
]}

Li, Xiangyan ^{[1
]}

Zhang, Yange ^{[1
]}

Xu, Yichun ^{[1
]}

Liu, Wei ^{[1
]}

Xie, Zhuoming ^{[1
]}

Liu, Rui ^{[1
]}

Luo, Guang-Nan ^{[2
]}

Liu, Xiang ^{[3
]}

Liu, C. S. ^{[1
]}

机构：

[1] Chinese Acad Sci, Inst Solid State Phys, HFIPS, Key Lab Mat Phys, Hefei 230031, Peoples R China

[2] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China

[3] Southwestern Inst Phys, POB 432, Chengdu 610041, Peoples R China

来源：

JOURNAL OF FUSION ENERGY | 2020年 / 39卷 / 06期

基金：

中国国家自然科学基金;

关键词：

Grain boundary; Interface; Tungsten; Simulation; Plasma facing materials;

D O I：

10.1007/s10894-020-00271-4

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Tungsten (W) has been considered as one of most promising candidates as plasma-facing materials in fusion reactors. However, the application of pure W is restricted due to its brittleness at room temperature and high ductile-to-brittle temperature. Much attention was paid to develop advanced W materials with a simultaneous strength and toughness enhancement over decades by introducing toughening elements, controlling the grain boundaries (GBs), specific phase boundary (PB) interface design and regulating the interface density. This paper reviews the recent advances of simulation and experiments on GB and PB interface design strategies for advanced W materials, including the GB strengthening by solute segregation, PB interface controlling by second phase nanoparticles, and fabrication of advanced W materials such as oxides or carbides dispersion strengthening W. Furthermore, the future research directions are indicated about the GB and PB interface design to improve the mechanical properties and irradiation performance for W materials.

引用

页码：342 / 354

页数：13

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