Removal of Deuterium in Lithium Titanate by Sweep Gas Exposure
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概要
- 論文の詳細を見る
Lithium titanate, Li2TiO3, was irradiated with deuterium ions with energy of 1.7 keV and then exposed to helium or helium-hydrogen mixed gas at different temperature, in order to evaluate the effect of exposure gas on removing deuterium from the pebbles. The amount of residual deuterium in the irradiated pebbles after the gas exposure was measured by thermal desorption spectroscopy. The mixing of hydrogen gas into helium gas enhanced the removal amount of deuterium. In other words, the amount of residual deuterium after the helium-hydrogen mixed gas exposure at low temperature was lower than that after the helium gas exposure. The ion irradiation followed by heating for the pebbles was repeated, and the residual amount of deuterium was measured. The residual amount increased with the number of irradiation/heating cycles. The result suggests that the tritium inventory in the blanket in a fusion reactor changes after the operation.
- 社団法人 プラズマ・核融合学会の論文
著者
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Hino Tomoaki
Laboratory Of Plasma Physics And Engineering Hokkaido University
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YAMAUCHI Yuji
Laboratory of Plasma Physics and Engineering, Hokkaido University
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Nobuta Yuji
Laboratory Of Plasma Physics And Engineering Hokkaido University
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Akiba Masato
Japan Atomic Energy Agency
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ENOEDA Mikio
Japan Atomic Energy Agency
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HINO Tomoaki
Laboratory of Plasma Physics and Engineering, Hokkaido University
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TSUCHIYA Akihito
Laboratory of Plasma Physics and Engineering, Hokkaido University
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