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Deuterium ion irradiation for tritium breeding material and evaluation for tritium inventories in test blanket module and blanket of a demonstration reactor

トリチウム増殖材への重水素照射とITERテストブランケット・モジュール及び原型炉ブランケットにおけるトリチウム吸蔵量の評価

日野 友明*; 柴田 博信*; 山内 有二*; 信太 祐二*; 鈴木 哲; 秋場 真人

Hino, Tomoaki*; Shibata, Hironobu*; Yamauchi, Yuji*; Nobuta, Yuji*; Suzuki, Satoshi; Akiba, Masato

The tritium produced in a tritium breeder of blanket has to be recovered under the temperature distribution to reduce the tritium inventory. Lithium titanate pebbles were irradiated by deuterium ions with different temperatures and ion fluences. The deuterium retained in the pebbles desorbed in forms of HD, D$$_{2}$$, HDO and D$$_{2}$$O. The amount of retained deuterium decreased for the temperature higher than 473 K, and became to zero for the temperature higher than 773 K. If the temperature range is taken from 573 to 1173 K in the solid breeder TBM, the tritium inventory is lower than 1 gram. However, in the demonstration reactor, the total tritium inventory of blankets becomes a few kilograms. For the reduction of the tritium inventory, the region with the low temperature region has to be significantly reduced.

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パーセンタイル:44.68

分野:Materials Science, Multidisciplinary

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