MOX reprocessing at TRP, 6; Study of solvent degradation

Hoshi, Takahiro; Kawaguchi, Yoshihito; Kitao, Takahiko ; Oyama, Koichi ; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi

For reprocessing nuclear spent fuel, in future, used for plutonium-thermal and fast-breeding reactor, density of DBP in extraction solvent on reprocessing Fugen MOX Type B fuel was measured. And we formulated an equation for increased density of DBP to estimate density of DBP in extraction cycle.

Language	:	Japanese
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Meeting title	:	日本原子力学会2008年春の年会
Held date	:	2008/03
Location (city)	:	吹田
Location (country)	:	日本
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Keywords	:	no keyword
Research Facility	:	再処理施設
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Registration No. : BB20073036
JAEA Abstracts No. :
Paper Submission No. :

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