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Ueta, Shohei; Mizuta, Naoki; Fukaya, Yuji; Goto, Minoru; Tachibana, Yukio; Honda, Masaki*; Saiki, Yohei*; Takahashi, Masashi*; Ohira, Koichi*; Nakano, Masaaki*; et al.
Nuclear Engineering and Design, 357, p.110419_1 - 110419_10, 2020/02
Times Cited Count:1 Percentile:11.54(Nuclear Science & Technology)The concept of a plutonium (Pu) burner HTGR is proposed to incarnate highly-effective Pu utilization by its inherent safety features. The security and safety fuel (3S-TRISO fuel) employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO) and yttria stabilized zirconia (YSZ) as an inert matrix. This paper presents feasibility study of Pu burner HTGR and R&D on the 3S-TRISO fuel.
Goto, Minoru; Demachi, Kazuyuki*; Ueta, Shohei; Nakano, Masaaki*; Honda, Masaki*; Tachibana, Yukio; Inaba, Yoshitomo; Aihara, Jun; Fukaya, Yuji; Tsuji, Nobumasa*; et al.
Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.507 - 513, 2015/09
A concept of a plutonium burner HTGR named as Clean Burn, which has a high nuclear proliferation resistance, had been proposed by Japan Atomic Energy Agency. In addition to the high nuclear proliferation resistance, in order to enhance the safety, we propose to introduce PuO-YSZ TRISO fuel with ZrC coating to the Clean Burn. In this study, we conduct fabrication tests aiming to establish the basic technologies for fabrication of PuO-YSZ TRISO fuel with ZrC coating. Additionally, we conduct a quantitative evaluation of the security for the safety, a design of the fuel and the reactor core, and a safety evaluation for the Clean Burn to confirm the feasibility. This study is conducted by The University of Tokyo, Japan Atomic Energy Agency, Fuji Electric Co., Ltd., and Nuclear Fuel Industries, Ltd. It was started in FY2014 and will be completed in FY2017, and the first year of the implementation was on schedule.
Ikeuchi, Hirotomo; Yano, Kimihiko; Ogino, Hideki; Saiki, Yohei*; Honda, Masaki*; Kinoshita, Hideaki*; Muta, Hiroaki*; Yamanaka, Shinsuke*
no journal, ,
In the case of Fukushima Daiichi Nuclear Power Station (1F) Accident, it is estimated that the fuel assemblies were damaged seriously and that fuel deburis deposits in the core or the bottom of vessel. The methodology of defueling such as cutting and core boring is considered referring the case of Three Mile Island Unit 2 (TMI-2) Accident. It is supposed that fuel debris have various characteristics depending on the location. Especially, the information on mechanical properties of fuel debris is important in order to select and develop the defueling technologies. In this work, (U,Zr)O as simulated debris including YO, CeO, CaO, which exist as a fisson product or a component of concrete and behavior as stabilizer for ZrO, was prepared and their mechanical properties were evaluated.
Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro; Saiki, Yohei*; Kakiuchi, Kazuo*; Kanaoka, Takuya*; Muta, Hiroaki*; Yamanaka, Shinsuke*
no journal, ,
no abstracts in English