Basic study on plasma facing materials by using hydrogen storage material

Saori Mera, Suguru Tanaka, A. Tonegawa, K. Kawamura, Kohnosuke Sato, Y. Matsumura, H. Uchida
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Abstract

Nuclear fusion is expected as one of the future energy source. Deuterium and Tritium are fuels. But most unreacted fuel is exhausted out of fusion reactor. Especially, Tritium is radioisotope and rarely exists in nature, so fuels recovery is necessary. Therefore, we propose a separation on divertor region by using hydrogen storage material. In this study, we have proposed fuel particles recovering on divertor with titanium in the type of a hydrogen storage material by using divertor simulator TPD-SheetIV via deuterium plasma. After deuterium plasma exposures, the samples were analyzed by thermal desorption spectroscopy (TDS). The temperatures of the samples were increased up to 1093K. As a result, the TDS measurement shows that deuterium is retained.
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用储氢材料制备等离子体表面材料的基础研究
核聚变有望成为未来能源的一种。氘和氚是燃料。但是大多数未反应的燃料都是从聚变反应堆中消耗掉的。特别是氚是放射性同位素,在自然界中很少存在,所以燃料回收是必要的。因此,我们提出利用储氢材料在导流器区域进行分离。在本研究中,我们提出了利用TPD-SheetIV型导流器模拟器通过氘等离子体在含钛的储氢材料导流器上回收燃料颗粒。在氘等离子体暴露后,用热解吸光谱(TDS)对样品进行分析。将样品的温度提高到1093K。结果,TDS测量表明氘被保留。
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