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Chikhray, Y.*; Askerbekov, S.*; Kenzhin, Y.*; Gordienko, Y.*; 石塚 悦男
Fusion Science and Technology, 76(4), p.494 - 502, 2020/05
被引用回数:1 パーセンタイル:10.11(Nuclear Science & Technology)The investigation of the mechanisms and dynamics of hydrogen isotopic interaction with solid surfaces (metals, ceramics, graphites, eutectics) in temperature and pressure ranges is important not only for the correct prediction of each isotope's evolution but also for substantiation of the safe operation of hydrogen-facing structural materials. The interaction of the hydrogen isotopes mix with the surface of solid metal or liquid eutectics is a complicated multistage H-D-T-O-solid interacting process depending on material property, environment, and the solid's surface parameters. To better understand the mechanisms of hydrogen isotopes interchange at a solid surface and to identify the limiting stages in the sorption-desorption processes, a reactor experiment of neutron irradiation was conducted with lithium-containing eutectics as tritium-generating media under the external flow of hydrogen. This work presents the model and results of its application to fitting the experimental results of tritium yield from the lithium-lead eutectics PbLiunder thermal neutrons irradiation at the IVG.1M reactor in Kazakhstan. The elaborated model and the approach used were also applied to the simulation of high temperature gas cooled reactor graphite corrosion in water vapors.
Kulsartov, T.*; Tazhibayeva, I.*; Gordienko, Y.*; Chikhray, E.*; 土谷 邦彦; 河村 弘; Kulsartova, A.*
Fusion Science and Technology, 60(3), p.1139 - 1142, 2011/10
被引用回数:14 パーセンタイル:70.87(Nuclear Science & Technology)チタン酸リチウム(LiTiO)は化学的安定性及び低い温度での良好なトリチウム放出特性の観点から核融合炉の固体増殖材料の候補材である。本論文は、高燃焼まで照射したLiTiO試料からのトリチウム及びヘリウム放出に関するものである。96%Li濃縮LiTiO微小球(直径1mm)をLi燃焼度約20%まで、650660Cの温度で220日間WWR-K炉で照射した。トリチウム及びヘリウムの放出は熱解離方法で行った。本材料からのトリチウム及びヘリウム放出を体積拡散律速とし、拡散係数及び活性化エネルギーを算出した結果、仮定したモデルと良い一致を示した。得られた拡散係数及び活性化エネルギーは、将来の核融合炉用増殖材料におけるガス放出機構の解明と運転温度評価に役立つ。