Tritium accumulation and release from Li2TiO3 during long-term irradiation in the WWR-K reactor

被引：17
|
作者：
Tazhibayeva, I. [1 ]
Beckman, I. [2 ]
Shestakov, V. [3 ]
Kulsartov, T. [1 ]
Chikhray, E. [3 ]
Kenzhin, E. [1 ]
Kiykabaeva, A. [3 ]
Kawamura, H. [4 ]
Tsuchiya, K. [4 ]
机构：
[1] Natl Nucl Ctr RK, Inst Atom Energy, Kurchatov 071100, Kazakhstan
[2] Moscow MV Lomonosov State Univ, Moscow 119991, Russia
[3] Kazakh State Univ, Alma Ata, Kazakhstan
[4] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan
来源：
JOURNAL OF NUCLEAR MATERIALS | 2011年 / 417卷 / 1-3期
关键词：
D O I：
10.1016/j.jnucmat.2010.12.133
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Proposed mathematical and software analysis of reactor experiments allowed interpretation of the experimental results of a tritium release study. Tritium was continuously generated by the reaction of lithium-6 with thermal neutrons for various thermal conditions of lithium metatitanate (Li2TiO3). The main gas release parameters were calculated in order to assess the potential use of lithium metatitanate in tritium breeders. These parameters were: gas release rate, tritium retention, retention time, activation energy for thermal desorption as HT, activation energy for volume diffusion as T+, and the corresponding pre-exponential (frequency) indexes. (C) 2010 Published by Elsevier B.V.
引用
收藏
页码：748 / 752
页数：5
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