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Report No.
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Characteristic of tritium release from Li$$_{2}$$TiO$$_{3}$$ under D-T neutron irradiation

Edao, Yuki; Kawamura, Yoshinori; Ochiai, Kentaro; Hoshino, Tsuyoshi; Takakura, Kosuke; Ota, Masayuki; Iwai, Yasunori; Yamanishi, Toshihiko; Konno, Chikara

Tritium generation and recovery studies on Li$$_{2}$$TiO$$_{3}$$ as a solid breeding material under neutron irradiation carried out in the Fusion Neutron Source (FNS) facility. A capsule with Li$$_{2}$$TiO$$_{3}$$ packed bed was put in a system which simulated an actual blanket system which built in beryllium blocks and lithium titanate ones. Estimated values of the amount of tritium generation by a numerical calculation agreed closely with experimental values. The capsule was heated up to 300$$^{circ}$$C, and helium, helium with water vapor, hydrogen or hydrogen/water vapor were selected as purge gas. In the case of purge by helium added water vapor, the ratio of HTO to total tritium release was 98%. In helium with hydrogen/water vapor purge, the ratio of HTO to total tritium release was 80%, which was confirmed that HTO released by isotope exchange reaction between water vapor and tritium. In helium with hydrogen purge, the ratio of HT to total tritium release was 60$$sim$$70%, which was shown that HT released by isotope exchange reaction between hydrogen gas and tritium. HTO released by water generation reaction between hydrogen in purge gas and oxygen in Li$$_{2}$$TiO$$_{3}$$ although water vapor was not added in purge gas. The ratio of HTO release seemed to be small under the deoxidized condition of the Li$$_{2}$$TiO$$_{3}$$ surface. Tritium release behavior in the Li$$_{2}$$TiO$$_{3}$$ depended on the composition of purge gas, and its chemical form was affected by the surface conditions of Li$$_{2}$$TiO$$_{3}$$.

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