STUDY OF TRITIUM AND HELIUM RELEASE FROM IRRADIATED LITHIUM CERAMICS Li2TiO3

被引：14

作者：

Kulsartov, T. ^{[1
]}

Tazhibayeva, I. ^{[1
]}

Gordienko, Yu ^{[1
]}

Chikhray, E. ^{[2
]}

Tsuchiya, K. ^{[3
]}

Kawamura, H. ^{[3
]}

Kulsartova, A. ^{[4
]}

机构：

[1] NNC RK, Inst Atom Energy, Kurchatov 071100, Kazakhstan

[2] SRI ETP al Farabi KazNSU, Alma Ata, Kazakhstan

[3] JAEA, Neutron Irradiat & Testing Reactor Ctr, Highashiibaraki, Ibaraki 3111393, Japan

[4] Nucl Technol Safety Ctr, Alma Ata 050020, Kazakhstan

来源：

FUSION SCIENCE AND TECHNOLOGY | 2011年 / 60卷 / 03期

关键词：

D O I：

10.13182/FST11-A12616

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

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 degrees C). This paper contains the results of the studies on tritium and helium release from the samples of irradiated lithium ceramics Li2TiO3.

引用

页码：1139 / 1142

页数：4

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