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Oxygen chemical diffusion in fast neutron reactor fuel U$$_{0.698}$$Pu$$_{0.289}$$Am$$_{0.013}$$O$$_{2-x}$$

Vauchy, R.  ; Horii, Yuta ; Hirooka, Shun ; Akashi, Masatoshi ; Sunaoshi, Takeo*; Nakamichi, Shinya  ; Saito, Kosuke

The oxygen chemical diffusion of fast neutron reactor MOX U$$_{0.698}$$Pu$$_{0.289}$$Am$$_{0.013}$$O$$_{2-x}$$ was investigated by thermogravimetric analysis between 1773 and 1923 K, using an innovative experimental procedure. At a given temperature, the oxygen chemical diffusion coefficients were shown to decrease when the Oxygen/Metal ratio decreases (in hypo-stoichiometry). The variations of the oxygen chemical diffusion coefficients as a function of temperature and oxygen partial pressure (hence oxygen stoichiometry) were paralleled to a defect chemistry model.

Language

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English

Journal

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Proceedings of 34th Nuclear Energy for New Europe (NENE2025)

Volume

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Number

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Pages

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p.232 - 238

Publication Year/Month

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2026/01

Meeting title

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34th Nuclear Energy for New Europe (NENE2025)

Held date

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2025/09

Location (city)

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Bled

Location (country)

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Slovenia

Patent information

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PDF

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Paper URL

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DOI for research data

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Link to research data related to this paper/report.

Keywords

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MOX Fuel; Oxygen diffusion; Manufacturing; Oxygen chemical diffusion coefficients; Defect chemistry

Research Facility

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Press Release

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JAEA R&D Navigator

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Cooperating Institute

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Accesses

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- Accesses

InCites™

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