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Chikhray, Y.*; Askerbekov, S.*; Kenzhin, Y.*; Gordienko, Y.*; Ishitsuka, Etsuo
Fusion Science and Technology, 76(4), p.494 - 502, 2020/05
Times Cited Count：1 Percentile：12.16(Nuclear Science & Technology)Chikhray, Y.*; Kulsartov, T.*; Shestakov, V.*; Kenzhina, I.*; Askerbekov, S.*; Sumita, Junya; Ueta, Shohei; Shibata, Taiju; Sakaba, Nariaki; Abdullin, Kh.*; et al.
Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), p.572 - 577, 2016/11
Application of SiC as corrosion-resistive coating over graphite remains important task for HTGR. This study presents the results of chemical interaction of the SiC gradient coating over the high-density IG-110 graphite with water vapor in the temperature up to 1673 K. The experiments at 100 Pa of water vapor showed that the passive reaction caused to form SiO
film on the surface of SiC coating. Active corrosion of SiC in 1Pa of water vapor leads to deposits of various carbon composites on its surface.
Ishitsuka, Etsuo; Motohashi, Jun; Hanawa, Yoshio; Komeda, Masao; Watahiki, Shunsuke; Mukanova, A.*; Kenzhina, I. E.*; Chikhray, Y.*
JAEA-Technology 2014-025, 77 Pages, 2014/08
JAEA-Technology-2014-025.pdf:43.46MB
It has been shown that tritium concentration in the primary coolant of the JMTR and JRR-3M increases during its operation. In this report, to clarify the tritium sources, the tritium release rate into the primary coolant in each operation cycle for the JMTR, JRR-3M and JRR-4 was evaluated. As a result, the tritium release rate is 
8 Bq/Wd in the JRR-4, which has not the beryllium core components installed, and no increase in the tritium concentration during reactor operation is observed. In contrast, the tritium release rate is about 10
95 and 60140 Bq/Wd in the JRR-3M and JMTR respectively, which cores contain beryllium components, and where the tritium content increases while reactor operates. It is also observed that the amount of released tritium is lower in the case of new beryllium components installation, and increases with the reactor operating cycle.
TiO
Kulsartov, T.*; Tazhibayeva, I.*; Gordienko, Y.*; Chikhray, E.*; Tsuchiya, Kunihiko; Kawamura, Hiroshi; Kulsartova, A.*
Fusion Science and Technology, 60(3), p.1139 - 1142, 2011/10
Times Cited Count：13 Percentile：69.64(Nuclear Science & Technology)no abstracts in English
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.
O-SiO Including CrPO
Nakamichi, Masaru; Kulsartov, T. V.*; Hayashi, Kimio; Afanasyev, S. E.*; Shestakov, V. P.*; Chikhray, Y. V.*; Kenzhin, E. A.*; Kolbaenkov, A. N.*
Fusion Engineering and Design, 82(15-24), p.2246 - 2251, 2007/10
Times Cited Count：25 Percentile：83.32(Nuclear Science & Technology)no abstracts in English
O-SiO including CrPO, Out-of-pile testsKulsartov, T. V.*; Hayashi, Kimio; Nakamichi, Masaru*; Afanasyev, S. E.*; Shestakov, V. P.*; Chikhray, Y. V.*; Kenzhin, E. A.*; Kolbaenkov, A. N.*
Fusion Engineering and Design, 81(1-7), p.701 - 705, 2006/02
Times Cited Count：41 Percentile：92.46(Nuclear Science & Technology)no abstracts in English
Kenzhina, I. E.*; Ishitsuka, Etsuo; Okumura, Keisuke; Takemoto, Noriyuki; Mukanova, A.*; Chikhray, Y.*
no journal, ,
Increase of tritium concentration in the primary coolant for research and testing reactors during reactor operation had been reported. To clarify the tritium sources, a curve of tritium release rate into the primary coolant for the JMTR and JRR-3M are evaluated. As a result, the tritium release rate is related with produced Li by (n,
) reaction from 
Be, and evaluation results of tritium release curve are shown as the dominant source of tritium release into the primary coolant for the JMTR and JRR-3M are beryllium components. Scattering of the tritium release rate with irradiation time were observed, and this phenomena in the JMTR occurred in earlier time than that of the JRR-3M.
