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*; et al.

Nuclear Engineering and Design, 357, p.110419_1 - 110419_10, 2020/02

https://doi.org/10.1016/j.nucengdes.2019.110419

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.

Prepardtion of Uranium-Plutonium Carbide-Based Fuels Simulating High Burnup by Carbothermic Reduction and Their Properties

; ; ; ;

JAERI-M 84-161, 30 Pages, 1984/09

JAERI-M-84-161.pdf:2.28MB

no abstracts in English

Examination that improves solubility of plutonium dioxide in MOX powder

Tanigawa, Masafumi; Kato, Yoshiyuki; Kurita, Tsutomu; Komatsuzaki, Mai*; Otaka, Akihiro*; Nakamichi, Hideo*

no journal, , 

no abstracts in English