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TiO
+ 5 mol% TiO lithium ceramics after long-term neutron irradiationChikhray, Y.*; Shestakov, V.*; Maksimkin, O.*; Turubarova, L.*; Osipov, I.*; Kulsartov, T.*; Kuykabayeba, A.*; Tazhibayeva, I.*; Kawamura, Hiroshi; Tsuchiya, Kunihiko
Journal of Nuclear Materials, 386?388, p.286 - 289, 2009/04
Times Cited Count：19 Percentile：76.21(Materials Science, Multidisciplinary)The PIE (Post Irradiation Examinations) results of LiTiO pebbles added with 5 mol% TiO after the long-term irradiation tests are described in this paper. 96 at% 
Li-enriched LiTiO pebbles were prepared as the irradiation specimens and these specimens were irradiated during 223 days at the reactor power of 6 MWt in the WWR-K of NNC-RK. After neutron irradiation, light-colored pebbles became gray-colored due to structure changes which generation of gray-colored inclusions with low density and microhardness. Crystal structure of the pebbles after the irradiation test were changed from the results of X-ray diffraction measurement. The value of maximum permissible load (pebble crash limit) at that was also low. The residual tritium in the pebbles was measured after the irradiation test.
TiO for fusion reactor blanketTazhibayeva, I. L.*; Kenzhin, E. A.*; Kulsartov, T. V.*; Kuykabayeva, A. A.*; Shestakov, V.*; Chikhray, E.*; Gizatulin, S.*; Maksimkin, O. P.*; Beckman, I. N.*; Kawamura, Hiroshi; et al.
Questions of Atomic Science and Technology, 2, p.3 - 11, 2008/00
Lithium titanate (LiTiO) was chosen as a tentative reference material from viewpoints of good tritium recovery at low temperatures and of low tritium inventory and chemical stability for the breeding blanket in fusion reactors. The results of the irradiation tests of LiTiO in the WWR-K of NNC-RK are described in this paper. 96at% Li-enriched LiTiO pebbles and disks were prepared as the irradiation specimens and these specimens were irradiated during 220 days (5350 hours) at the reactor power of 6 MWt. Tritium release was measured continuously during irradiation tests and tritium release properties were evaluated. The mechanics describing generation and release of tritium from the irradiated LiTiO were analyzed. There was estimated tritium loss due to recoil energy and binding of tritium in HTO, and there was calculated stationary tritium release due to diffusion under constant temperature and under thermal cycling.
TiO+5% mole TiO irradiated in WWR-K reactor for solid ceramic blanket of fusion reactorTazhibayeva, I. L.*; Kulsartov, T.*; Kenzhin, E. A.*; Maksimkin, O. P.*; Doronina, T. A.*; Silnyagina, N. S.*; Turubarova, L. G.*; Tsai, K. V.*; Zheltov, D. A.*; Kashirskiy, V. V.*; et al.
Questions of Atomic Science and Technology; Series the Thermonuclear Fusion, 1, p.3 - 11, 2008/00
The paper contains and analyzes the results of integrated material studies of lithium ceramic LiTiO + 5% mole TiO irradiated in reactor WWR-K during 5,350 hours under controlled conditions taking into account effects of tritium generated in the course of irradiation. The changes in density, microstructure, phase and chemical composition, strength and microhardness were studies; lithium burn-up level and tritium residual content were defined. The significant influence of radiation-thermal impacts on structure and properties of ceramic samples were observed. It was shown that irradiation resulted in lithium ceramics softening, at that this effect depended on irradiation temperature. It was discovered the radiation change of phase composition of lithium ceramic.
TiO for fusion reactor blanketTazhibayeva, I. L.*; Kenzhin, E. A.*; Chachrov, P. V.*; Arinkin, F. M.*; Gasatulin, Sh. Kh.*; Bekamukhabetov, E. S.*; Shestakov, V. P.*; Chikhray, E. V.*; Kulsartov, T. V.*; Kuykabaeva, A. A.*; et al.
Questions of Atomic Science and Technology; Series the Thermonuclear Fusion, 2, p.3 - 10, 2007/00
no abstracts in English
