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Report No.

Development of science-based fuel technologies for Japan's Sodium-Cooled Fast Reactors

Kato, Masato   ; Hirooka, Shun ; Ikusawa, Yoshihisa   ; Takeuchi, Kentaro ; Akashi, Masatoshi ; Maeda, Koji  ; Watanabe, Masashi  ; Komeno, Akira ; Morimoto, Kyoichi 

Uranium and plutonium mixed oxide (MOX) fuel has been developed for Japan sodium-cooled fast reactors. Science based fuel technologies have been developed to analyse behaviours of MOX pellets in the sintering process and irradiation conditions. The technologies can provide appropriate sintering conditions, irradiation behaviour analysis results and so on using mechanistic models which are derived based on theoretical equations to represent various properties.



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