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Development of security and safety fuel for Pu-burner HTGR, 3; Fuel design and nuclear thermal design

Goto, Minoru; Ueta, Shohei; Aihara, Jun; Fukaya, Yuji; Inaba, Yoshitomo; Tachibana, Yukio; Kunitomi, Kazuhiko; Okamoto, Koji*

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.

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