饲养员(动物)
氚
锂(药物)
材料科学
钛酸锂
聚变能
陶瓷
辐照
放射化学
氦
氧化锂
核工程
毯子
核物理学
等离子体
复合材料
化学
磷酸钒锂电池
原子物理学
物理
热力学
锂离子电池
电池(电)
医学
功率(物理)
内分泌学
工程类
作者
Timur Kulsartov,I. Tazhibayeva,Yuriy Gordienko,Yevgen Chikhray,Kunihiko Tsuchiya,Hiroshi Kawamura,A.V. Kulsartova
标识
DOI:10.13182/fst11-a12616
摘要
Lithium-based oxide ceramics are considered as the candidate materials for solid breeders of future fusion reactors' blankets. Breeder's goal is effective, safe and reliable production of tritium as a result of lithium-neutron reactions. Main candidates as a breeder material are Li2O, Li4SiO4, Li2TiO3 and Li2ZrO3, which are able to keep their physical-chemical properties despite of lithium burn-up. Lithium metatitanate Li2TiO3 attracts the great attention due to its chemical stability and high speed of tritium release under low temperatures (from 200 to 400°C). This paper contains the results of the studies on tritium and helium release from the samples of irradiated lithium ceramics Li2TiO3.
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