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.

Language	:	English
Journal	:	Proceedings of 19th Pacific Basin Nuclear Conference (PBNC 2014) (USB Flash Drive)
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Number	:
Pages	:	12 Pages
Publication Year/Month	:	2014/08
Meeting title	:	19th Pacific Basin Nuclear Conference (PBNC 2014)
Held date	:	2014/08
Location (city)	:	Vancouver
Location (country)	:	Canada
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Keywords	:	no keyword
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Registration No. : BB20132596
JAEA Abstracts No. : 42001480
Paper Submission No. : 15108

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