Oxygen potentials of UO2 fuel simulating high burnup.

A study on ThO2–LaO1.5 solid solution: Lattice thermal expansion measurements and XPS studies

“…The solubility of LaO 1.5 in ThO 2 at 1473 K measured to be in the range 49.7-50.3 mol% [7]. The changes in lattice parameter of thoria with possible fission product additions have already been reported in the literature [8][9][10]. However, not much data are available in open literature on the thermal expansion characterisitics of ThO 2 -LaO 1.5 solid solutions.…”

Phase relation and bulk thermal expansion studies in thoria–neodia system

“…In the latter two classes, the rare-earth oxides Ln 2 O 3 (Ln = La, Ce, Nd, Y, Sm, Gd or Eu), ZrO 2 , alkali oxides M 2 O (M = Rb, Cs), alkaline-earth oxides MO (M = Sr, Ba) and their solid solutions with fuel matrix are most common. Mainly the rare-earth oxides are known to be soluble in ThO 2 and (U,Th)O 2 fuels [3][4][5]. The behaviour of nuclear fuel during irradiation is highly dependent on the physico-chemical and thermo-physical properties of the fuel material, and their variation with temperature and burn up.…”

Chemical thermodynamic analysis of americium-containing UO2 and (U,Pu)O2

“…Am 0.5 )O 2−x and (U 0.685 Pu 0.270 Am 0.045 )O 2−x , together with those of (U,RE)O 2−x data[8,21,22], as a function of U valence. It is seen that the agreement of oxygen potentials between (U 0.5 Am 0.5 )O 2−x and (U 0.685 Pu 0.270 Am 0.045 )O 2−x is good above U valence of 4.7, and these potentials fall between those of (U,La)O 2−x and (U,Gd/Nd)O 2−x .…”