Study of Li2TiO3+5 mol% TiO2 lithium ceramics after long-term neutron irradiation

被引:23
作者
Chikhray, Y. [1 ]
Shestakov, V. [1 ]
Maksimkin, O. [2 ]
Turubarova, L. [2 ]
Osipov, I. [2 ]
Kulsartov, T. [3 ]
Kuykabayeba, A. [3 ]
Tazhibayeva, I. [3 ]
Kawamura, H. [4 ]
Tsuchiya, K. [4 ]
机构
[1] Kazakh Natl Univ, Alma Ata, Kazakhstan
[2] Inst Nucl Phys, Alma Ata, Kazakhstan
[3] Natl Nucl Ctr, Kurchatov, Kazakhstan
[4] JAEA, Oarai, Ibaraki, Japan
关键词
D O I
10.1016/j.jnucmat.2008.12.111
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Given work presents the results of complex material-science studies of I mm diameter ceramic pebbles manufactured of Li2TiO3 + 5 mol% TiO2 ceramics before and after long-time neutron irradiation. Ceramic samples were placed in specially ampoules (six items) made of stainless steel Cr18Ni10Ti which were vacuumized and filled with helium. Irradiation of ampoules was carried out in the loop channel of WWRK reactor (Almaty, Kazakhstan) during 223 days at 6 MW power. After irradiation light-colored pebbles became grey-colored due to structure changes which generation of grey-colored inclusions (lithium oxide) with low density and microhardness. There is a radiation softening of lithium ceramic and that effect is higher for lower irradiation temperature 760 K than for 920 K. The value of maximum permissible load (pebble crash limit) at that is low and comprises similar to 37.9 N. The content of residual tritium is higher for ceramic irradiated at 760 K (6.6 +/- 0.6 x 10(11) Bq/kg) than for ceramic irradiated at 920 K (17 +/- 3 x 10(10) Bq/kg). The size change indicates that pebble increase more after irradiation at 760 K than at 920 K where the bigger portion of tritium leaves the pebble. X-ray analysis shows radiation modification of Li2TiO3 + 5 mol% TiO2 phase composition and generation of new phases: LiTi2O4, LiTiO2 and Li4Ti5O12. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:286 / 289
页数:4
相关论文
共 4 条
[1]   Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor [J].
Chikhray, Y. ;
Shestakov, V. ;
Kulsartov, T. ;
Tazhibayeva, I. ;
Kawamura, H. ;
Kuykabaeva, A. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) :1028-1032
[2]  
Shestakov V, 2005, FUSION SCI TECHNOL, V47, P1084
[3]   Development of wet process with substitution reaction for the mass production of Li2TiO3 pebbles [J].
Tsuchiya, K ;
Kawamura, H .
JOURNAL OF NUCLEAR MATERIALS, 2000, 283 :1380-1384
[4]  
TSUCHIYA K, DATA BASE TRITIUM SO