材料科学
脆化
热冲击
钨
铼
再结晶(地质)
分流器
聚变能
兴奋剂
辐照
等离子体
复合材料
冶金
核物理学
托卡马克
光电子学
古生物学
物理
生物
作者
Shuhei Nogami,G. Pintsuk,Kazuma Matsui,Satoshi Watanabe,M. Wirtz,Th. Loewenhoff,Akira Hasegawa
出处
期刊:Physica Scripta
[IOP Publishing]
日期:2020-01-01
卷期号:T171: 014020-014020
被引量:13
标识
DOI:10.1088/1402-4896/ab3dcc
摘要
High ductile-to-brittle transition temperature, recrystallization-induced embrittlement, and neutron-irradiation-induced embrittlement are potential drawbacks related to the mechanical properties of tungsten (W) for plasma facing materials of fusion reactor divertors. To improve the mechanical properties, resistance to recrystallization and neutron irradiation, W materials modified by potassium doping and alloying by rhenium have been developed. In this paper, thermal shock behaviors of these W materials under high heat flux tests were investigated, which simulated an edge localized mode of plasma occurring in fusion reactors as a transient event. The thermal shock tests were performed with an electron beam facility, JUDITH 1, and post-mortem analyses to evaluate the damage caused by the thermal shock tests were carried out.
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