## Abstract

The oxygen potential change of irradiated uranium dioxide and urania-plutonia mixed oxide fuels, which is caused by the formation of solid solutions of some fission product metals with the fuel oxides, was calculated using the intra-cation complex model. It assumes weak-bound complexes between the cations of relatively positive and negative charges with respect to U^{4+}. Partial molar entropy of oxygen, Δ S ̄_{O2}, was derived by differentiating the logarithm of the number of ways of arranging the cationic defects and complexes over the cation sublattices. The fission product metals which dissolve into the fuel matrix were classified into +2, +3 and +4 valence state ion groups, and their effect on Δ G ̄_{O2} was clarified in the equations of Δ G ̄_{O2} representation. Comparison of the calculated results with the Δ G ̄_{O2} values for irradiated fuels as well as for the fuels containing some fission product simulant cations revealed that agreement was good, showing that the Δ G ̄_{O2} change on irradiation can be expressed as a function of M^{3+} fraction.

Original language | English |
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Pages (from-to) | 70-80 |

Number of pages | 11 |

Journal | Journal of Nuclear Materials |

Volume | 201 |

Issue number | C |

DOIs | |

Publication status | Published - 1993 May 2 |

## ASJC Scopus subject areas

- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering

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