Oxygen potential of a prototypic Mo-cermet fuel containing plutonium oxide

Miwa, Shuhei ; Osaka, Masahiko ; Nozaki, Takahiro*; Arima, Tatsumi*; Idemitsu, Kazuya*

Oxygen potential of a prototypic Mo-cermet fuel containing PuO $_{2-x}$ was experimentally determined. It was shown that the oxygen potentials of Mo-cermet fuel containing PuO $_{2-x}$ were the same as those of pure PuO $_{2-x}$ . It was also confirmed that the gradual oxidation of the Mo matrix occurred only above the oxygen potential of Mo/MoO $_{2}$ . It is concluded that the oxidation-reduction behavior of the Mo-cermet fuel can be evaluated individually for each phase of actinides oxide and Mo matrix. Better phase structures of the Mo-cermet fuel for taking full advantage of the oxidation-reduction controllability were suggested by the confinement of the actinides oxide phase with Mo.

Language	:	English
Journal	:	Journal of Nuclear Materials
Volume	:	465
Number	:
Pages	:	p.840 - 842
Publication Year/Month	:	2015/10
Meeting title	:	Nuclear Materials Conference 2014 (NuMat 2014)
Held date	:	2014/10
Location (city)	:	Clearwater
Location (country)	:	U.S.A.
Patent information	:
PDF	:
Paper URL	:	https://doi.org/10.1016/j.jnucmat.2015.06.004
DOI for research data	:
Keywords	:	福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
Research Facility	:	AGF(照射燃料試験施設)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	九州大学

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Registration No. : BB20142098
JAEA Abstracts No. : 44000953
Paper Submission No. : 17641

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