Emissivity measurement of tungsten plasma facing components of the WEST tokamak
Emissivity measurement of tungsten plasma facing components of the WEST tokamak
复制标题
WEST 托卡马克面向钨等离子体的组件的发射率测量
DOI：
10.1016/j.fusengdes.2019.111328
复制
发表时间：
2019
影响因子：
1.7
通讯作者：
M. Wirtz
中科院分区：
文献类型：
--
作者：
J. Gaspar;C. Pocheau;Y. Corre;N. Ehret;D. Guilhem;M. Houry;T. Loarer;T. Loewenhoff;C. Martin;C. Pardanaud;G. Pintsuk;M. Richou;F. Rigollet;H. Roche;G. Sepulcre;M. Wirtz
由于钨(W)已被选为热核实验堆偏滤器目标的材料，因此必须了解红外(IR)波长范围内的发射率。研制了一套专用的发射率测量装置，测量了发射率的波长范围为1.70-4.75 μm，温度范围为200-850 °C。本文给出了来自主动冷却的块状钨组件(类热核实验堆)和西偏滤器镀钨石墨组件的W样品的发射率测量结果。文中还研究了在熔合机中观察到的由瞬时热载荷产生的表面损伤样品，包括微裂纹和裂纹网络。给出并讨论了它们对波长、温度和表面态的依赖关系。
Since tungsten (W) has been selected as material for the ITER divertor target the knowledge of the emissivity in the infrared (IR) wavelength range becomes mandatory. A dedicated setup has been developed to measure the emissivity in the wavelength range 1.7–4.75 μm and the temperature domain 200–850 °C. The paper presents the emissivity measurements on W samples coming from actively cooled bulk W components (ITER-like) and W-coated graphite component of the WEST divertor. W samples with damaged surfaces generated by transient heat load as those observed in fusion machines, including micro-cracks and crack network, are also investigated. The dependence on wavelength, temperature and surface state are shown and discussed.