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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Selection of candidate doped graphite materials as plasma facing components for HT-7U device
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Selection of candidate doped graphite materials as plasma facing components for HT-7U device

机译:选择候选掺杂石墨材料作为HT-7U器件的等离子面对面部件

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摘要

Selection of candidate materials for plasma facing material (PFM) in HT-7U device, and plasma-wall interactions are critically important to reach high plasma performance. Based on concentrated research on multi-element doped graphite containing B, Si and Ti, two kinds of doped graphites have been chosen as candidates for PFM in HT-7U. Doped graphite GBST1308 with the dopant concentration of 1% B, 2.5% Si, 7.5% Ti was developed as low-Z PFM for reducing the chemical sputtering and suppressing the radiation enhanced sublimation, and successfully used as the new limiter material in last two campaigns of HT-7 tokamak experiments. Doped graphite with the composition of 2.5% Si, 7.5% Ti has improved mechanical properties and thermal conductivity of 314 W/m K at room temperature. TDS and high heat flux experiments results demonstrated that such doped graphites are promising candidate plasma facing components for HT-7U. (C) 2003 Elsevier Science B.V. All rights reserved. [References: 11]
机译:在HT-7U设备中选择用于等离子体处理材料(PFM)的候选材料以及等离子体与壁之间的相互作用对于实现高等离子体性能至关重要。在对含B,Si和Ti的多元素掺杂石墨进行集中研究的基础上,选择了两种掺杂石墨作为HT-7U中PFM的候选材料。掺杂剂浓度为1%B,2.5%Si,7.5%Ti的掺杂石墨GBST1308被开发为低Z PFM,以减少化学溅射并抑制辐射增强的升华,并在最近的两次攻势中成功用作新的限制剂材料HT-7托卡马克实验组成为2.5%Si,7.5%Ti的掺杂石墨在室温下具有改善的机械性能和314 W / m K的导热率。 TDS和高热通量实验结果表明,这种掺杂石墨是HT-7U的有希望的面向等离子体的候选组分。 (C)2003 Elsevier Science B.V.保留所有权利。 [参考:11]

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