Lattice parameter of Am, Np bearing MOX fuel: an empirical potential study

We report an investigation of the effect of a low Am impurity content on bulk and point defect properties of mixed actinide oxide (U,Pu)O[Formula: see text]. Using the generalized gradient approximation, (GGA + U) we study [Formula: see text] with z = 3 and 6%. Several of its bulk properties have never been reported in the literature or are poorly known. The Hubbard term U is used to take into account the strong correlation effects related to the actinide 5f electrons. We find an electronic charge transfer between uranium and americium cations in the bulk crystal. Am(+IV) cations tend to easily reduce to Am(+III), and this reduction of Am(+IV) is compensated by the oxidation of U(+IV) to U(+V) in stoichiometric compounds. In turn, oxygen hypostoichiometry is accommodated by the reduction of U(+V) cations [which result from the presence of Am (+III) cations] before any reduction of the Pu cations. Furthermore, we show that Am induces a significant increase in the mixing enthalpy as well as a decrease in the lattice parameter of the (U,Pu)O[Formula: see text] solid solution, which is in agreement with early experimental studies. Finally, we show that americium facilitates the formation of oxygen vacancies in (U,Am)O[Formula: see text] compared to UO[Formula: see text], whereas it induces an increase in the formation energy of oxygen vacancies in (U,Pu,Am)O[Formula: see text] compared to (U,Pu)O[Formula: see text].

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Lattice parameter of Am, Np bearing MOX fuel: an empirical potential study

Cited by 3 publications

References 39 publications

Development of an interatomic potential for mixed uranium-americium oxides and application to the determination of the structural and thermodynamic properties of (U,Am)O2 with americium contents below 50%

Development of an interatomic potential for mixed uranium-americium oxides and application to the determination of the structural and thermodynamic properties of (U,Am)O2 with americium contents below 50%

Thorium fuel revisited

Investigation of the bulk and point defect properties in uranium–plutonium mixed oxides (U,Pu)O2 using DFT+U: Effect of a low americium content

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