材料科学
分流器
高温计
核工程
等离子体
锡
热流密度
钨
热成像
梁(结构)
辐照
分析化学(期刊)
温度测量
光学
红外线的
托卡马克
核物理学
冶金
传热
化学
物理
工程类
热力学
量子力学
色谱法
作者
F.L. Tabarés,E. Oyarzábal,D. Alegre,D. Tafalla,K. J. McCarthy,A. de Castro,E. Ascasíbar,A. Soleto,Iván Fernández,R. C. Carrasco,Fernando Martı́n,J.A. Sebastián,Jesús Gómez-Manchón,A. Pereira,A. de la Peña
标识
DOI:10.1016/j.fusengdes.2022.113373
摘要
The OLMAT (Optimization of Liquid Metal Advanced Targets) facility has recently undergone the commissioning and start-up phases. Solid Titanium-Zirconium- Molybdenum (TZM) alloy and liquid tin (Sn) metallic targets were exposed to a hydrogen neutral beam injector (NBI) particle flux with power densities up to 58 ± 14 MW/m2, pulse duration up to 150 ms, and repetition rates up to 2 pulses/minute. These beam parameters are well above the estimates based on the typical performance of this NBI system when used for heating plasmas in the TJ-II stellarator. The parameters of the plasma generated through the interaction of the fast (32.5 keV) neutrals and ions and the solid were characterized by spectroscopic methods while surface temperature and total absorbed power were followed using pyrometry, infrared (IR) thermography, and calorimetry, respectively. Targets were visually monitored during the exposure and microscopically analyzed ex-situ. Electrical isolation of the target permitted recording the floating voltage during irradiation as well as for active biasing tests. In this work, a description of the facility, its operating parameters, and firsts results are provided and assessed as a new High Heat Flux (HHF) Facility for testing solid and liquid metal divertor targets under reactor-relevant heat load conditions.
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