Oxygen chemical diffusion in hypo-stoichiometric MOX

Kato, Masato ; Morimoto, Kyoichi ; Tamura, Tetsuya*; Sunaoshi, Takeo*; Konashi, Kenji*; Aono, Shigenori; Kashimura, Motoaki

Plutonium and uranium mixed oxide (MOX) has been developed to use as a core fuel of the fast reactor. The oxygen to metal ratio (O/M) of the MOX fuel is an important parameter to control the FCCI. The oxygen potential and the oxygen diffusion coefficient of the MOX are essential data to understand the oxygen behaviour in MOX. The oxygen potentials of the MOX were measured with accuracy as a function of O/M and temperatures in the previous work. In this work the oxygen chemical diffusion coefficient in (Pu $_{0.2}$ U $_{0.8}$ )O $_{2-x}$ and (Pu $_{0.3}$ U $_{0.7}$ )O $_{2-x}$ were investigated using thermo gravimetric technique. The kinetics of the reduction processes of (Pu $_{0.2}$ U $_{0.8}$ )O $_{2-x}$ and (Pu $_{0.3}$ U $_{0.7}$ )O $_{2-x}$ were measured by TG-DTA method. The oxygen chemical diffusion coefficients have been estimated from the reduction curves. It was concluded that the oxygen chemical diffusion coefficient in (Pu $_{0.3}$ U $_{0.7}$ )O $_{2-x}$ is a smaller than that of (Pu $_{0.2}$ U $_{0.8}$ )O $_{2-x}$ .

Language	:	English
Journal	:	Journal of Nuclear Materials
Volume	:	389
Number	:	3
Pages	:	p.416 - 419
Publication Year/Month	:	2009/06
Meeting title	:	Plutonium Futures, The Science 2006; A Topical Conference on Plutonium and Actinides
Held date	:	2006/07
Location (city)	:	Pacific Grove
Location (country)	:	U.S.A.
Patent information	:
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Paper URL	:	https://doi.org/10.1016/j.jnucmat.2009.02.018
DOI for research data	:
Keywords	:	no keyword
Research Facility	:	プルトニウム燃料製造施設
Press Release	:
Article of JAEA R&D Review	:
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Registration No. : BB20051118
JAEA Abstracts No. : 37000712
Paper Submission No. : 5748

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