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C) conditionsOkamoto, Ryo*; Matsuura, Hideaki*; Ida, Yuma*; Koga, Yuki*; Suganuma, Takuro*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; et al.
no journal, ,
It has been proposed that lithium rods, which are cylindrical lithium compounds, are loaded into a HTGR and tritium for initial fusion reactors is produced by 
Li(n,
)T reaction. In this study, it was discussed that the lithium rods are covered with zirconium layers to prevent the produced tritium leak. The solubility and diffusion coefficient of hydrogen in zirconium were measured and the effectiveness of the zirconium layers on prevention of tritium leakage was estimated with the measured values. As a result, the tritium leakage ratio with the zirconium layers was estimated two orders lower than that without the zirconium layers, and hence it was considered that the zirconium layer is very effective on the prevention of the tritium leakage.
Suematsu, Senri*; Katayama, Kazunari*; Izumino, Junichi*; Matsuura, Hideaki*; Otsuka, Teppei*; Fukada, Satoshi*; Goto, Minoru; Nakagawa, Shigeaki
no journal, ,
It has been proposed that lithium compounds are loaded into a HTGR and tritium for initial fusion reactors is produced by Li(n,)T reaction. Coating PyC layer on the lithium compounds could be one of the method for preventing the produced tritium leakage. In this study, hydrogen permeation experiment was performed to obtain tritium transmission coefficient in PyC, which is an important value to estimate the amount of the tritium leakage.
Koga, Yuki*; Matsuura, Hideaki*; Okamoto, Ryo*; Ida, Yuma*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru; Nakagawa, Shigeaki; Ishitsuka, Etsuo; Nagasumi, Satoru; et al.
no journal, ,
Large quantity of tritium is demanded for starting up of fusion reactor and engineering test using tritium for fusion blanket system. Tritium production, by Li(n, )T reaction using the high temperature gas-cooled reactor (HTGR), has been proposed and the method to produce tritium by loading the lithium rods as burnable poison in the reactor core has been studied. In this presentation, the design of lithium rods to be loaded to High Temperature engineering Test Reactor (HTTR) and its irradiation test plan to demonstrate tritium production are presented.
Susukida, Maho*; Fujimoto, Nozomu*; Honda, Yuki
no journal, ,
no abstracts in English
Michino, Yudai*; Fujimoto, Nozomu*; Honda, Yuki
no journal, ,
no abstracts in English
Son, E.*; Sheikh, Md. A. R.*; Matsumoto, Tatsuya*; Morita, Koji*; Matsuba, Kenichi; Toyooka, Junichi; Tagami, Hirotaka; Kamiyama, Kenji
no journal, ,
To clarify the sedimentation behavior of fuel debris particles formed by molten fuel-coolant interaction in core disruptive accidents of sodium-cooled fast reactors, experiments pouring mixed particles simulating fuel debris into a water pool were conducted. In the experiments, effects of experimental parameters on the characteristics of particle bed formation were investigated. Based on the results of the experiments, an empirical correlation to predict quantitatively the center height of the bed composed of mixed particles with different sizes was developed. Bed height predicted using the correlation agreed well with the experimental results. Applicability of the developed correlation to the prediction of the center height of the bed composed of mixed particles with different sizes was confirmed.