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Aihara, Jun; Goto, Minoru; Inaba, Yoshitomo; Ueta, Shohei; Sumita, Junya; Tachibana, Yukio
Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), p.814 - 822, 2016/11
Japan Atomic Energy Agency (JAEA) has started R&D for apply SiC/C mixed matrix to fuel element of high temperature gas-cooled reactors (HTGRs) to improve oxidation resistance of fuel. Nuclear thermal design of HTGR with SiC/C mixed matrix fuel compacts was carried out as a part of above R&Ds. Nuclear thermal design was carried out based on a small sized HTGR for developing countries, HTR50S. Maximum enrichment of uranium is set to be 10 wt%, because coated fuel particles with 10 wt% uranium have been fabricated in Japan. Numbers of kinds of enrichment and burnable poisons (BPs) were set to be same as those of original HTR50S (3 and 2, respectively). We succeeded in nuclear thermal design of a small sized HTGR which performance was equivalent to original HTR50S, with SiC/C mixed matrix fuel compacts. Based on nuclear thermal design, intactness of coated fuel particles was evaluated to be kept on internal pressure during normal operation.
Goto, Minoru; Ueta, Shohei; Aihara, Jun; Fukaya, Yuji; Inaba, Yoshitomo; Tachibana, Yukio; Kunitomi, Kazuhiko; Okamoto, Koji*
no journal, ,
In this study, a feasibility of the coated fuel particle for a plutonium burner High Temperature Gas-cooled Reactor (HTGR) is evaluated by calculating the inner pressure. Additionally, a feasibility of the reactor core is also evaluated by calculating the nuclear characteristics and the fuel temperature. This study is started in 2014 and will be completed in 2017. In 2014, the calculation codes and the input files for the evaluations were prepared.
Goto, Minoru; Inaba, Yoshitomo; Aihara, Jun; Ueta, Shohei; Tachibana, Yukio
no journal, ,
JAEA has performed the research and development of the SiC matrix fuel, which is an oxidation resistant fuel against an air ingress accident, to establish the fundamental technologies. In this study, a nuclear thermal design was performed for the HTGR with the SiC matrix fuel.
Goto, Minoru; Nakagawa, Shigeaki; Matsuura, Hideaki*; Katayama, Kazunari*
no journal, ,
JAEA and Kyushu university have studied the tritium production method using high temperature gas-cooled reactors (HTGR) for initial fusion reactors. In this method, lithium compounds are loaded into the reactor core and tritium is produced with 
Li(n,
)T reaction. We studied about the optimization of a lithium loading method, an effective tritium containment method and the nuclear thermal design of a lithium loaded HTGR, and consequently we confirmed the feasibility of the tritium production method. This paper describes the feasibility of the nuclear thermal design of the lithium loaded HTGR tritium production.