Study on plutonium burner high temperature gas-cooled reactor in Japan; Introduction scenario, reactor safety and fabrication tests of the 3S-TRISO fuel

Ueta, Shohei ; Mizuta, Naoki ; Fukaya, Yuji ; Goto, Minoru ; Tachibana, Yukio ; Honda, Masaki*; Saiki, Yohei*; Takahashi, Masashi*; Ohira, Koichi*; Nakano, Masaaki*; Ohashi, Kazutaka*; Okamoto, Koji*

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 $_{2}$ ) 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.

Language	:	English
Journal	:	Nuclear Engineering and Design
Volume	:	357
Number	:
Pages	:	p.110419_1 - 110419_10
Publication Year/Month	:	2020/02
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Paper URL	:	https://doi.org/10.1016/j.nucengdes.2019.110419
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	High temperature gas-cooled reactor; Plutonium(Pu)-burner; TRISO coated fuel particle; Zirconium carbide; Reactor safety; Spent fuel disposal; HTGR; ZrC
Research Facility	:	HTTR(高温工学試験研究炉)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	富士電機; 東京大学; 原子燃料工業

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Web of Science® Times Cited Count	:	Times Cited Count： If you would like to get the latest times cited, please access the Web of Science®. http://www.webofknowledge.com/wos
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Registration No. : AA20190064
JAEA Abstracts No. : 48000122
Paper Submission No. : 22473

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