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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：11.8(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 Pb
Li
under 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.
山西 敏彦*; 柿内 秀樹*; 田内 広*; 山本 徳洋; 山本 一良*
no journal, ,
One of the essential subjects for the contaminated water at Fukushima Daiichi Nuclear Power Station is to serve technical data for handling the water, over a long period. All the radio nuclides other than tritium in the water can be treated by multi-nuclide removal equipment (advanced liquid processing system). However, it is not easy task to remove tritium. For this reason, a series of technical discussions has been carried out at a task force (Tritium Water Task Force) to handle the tritiated water after the treatment by the advanced liquid processing system. As of March 2016, 820,000 m
of the contaminated water has been stored within tanks, and 620,000 m water has been treated by the multi-nuclide removal equipment. The concentration of tritium in the water is about 0.3 - 3.3 million Bq/litter. Various options for the treatment of the tritiated water; such as off shore release, geosphere injection, underground burial, and vapor or hydrogen release; have been discussed. The discussions have been carried out from viewpoint of technical and regulatory feasibility. Some pre-treatment methods, such as dilution and isotope separation, have also been discussed. A series of discussions on the isotope separation has been carried out with actual experimental tests. Some valuable results have been produced through the tests. This report presents a summary of the above-mentioned technical discussions on the tritiated water at Fukushima Daiichi Nuclear Power Station. Some recent conditions of the tritiated water will also be introduced.
