Thermal conductivity measurement of uranium–plutonium mixed oxide doped with Nd/Sm as simulated fission products

Breaking the hard-sphere model with fluorite and antifluorite solid solutions

(2023) Romain Vauchy et al.   Scientific Reports

Fission products speciation in nuclear fuel: Synthesis and characterisation of mixed oxide (U,Pu)O2 SIMfuel

(2023) Rafael Caprani et al.   Journal of Nuclear Materials

Oxygen potential of neodymium-doped U0.817Pu0.180Am0.003O2± uranium–plutonium–americium mixed oxides at 1573, 1773, and 1873K

(2023) Romain Vauchy et al.   Journal of Nuclear Materials

Three-dimensional microstructural characterization of FBR MOX fuel and the contribution of microstructural features to the thermal conductivity of the fuel

(2022) Casey McKinney et al.   JOURNAL OF NUCLEAR MATERIALS

Effect of O/M ratio on sintering behavior of (Pu0.3U0.7)O2-x

(2020) Shinya Nakamichi et al.   JOURNAL OF NUCLEAR MATERIALS

Charge compensation mechanisms in Nd-doped UO2 samples for stoichiometric and hypo-stoichiometric conditions: Lack of miscibility gap

(2020) Bernardo Herrero et al.   JOURNAL OF NUCLEAR MATERIALS

High temperature measurements and condensed matter analysis of the thermo-physical properties of ThO2

(2018) T. R. Pavlov et al.   Scientific Reports

Actinide Oxidation State and O/M Ratio in Hypostoichiometric Uranium–Plutonium–Americium U0.750Pu0.246Am0.004O2–x Mixed Oxides

(2016) Romain Vauchy et al.   INORGANIC CHEMISTRY

Thermal expansion measurement of (U,Pu)O 2-x in oxygen partial pressure-controlled atmosphere

(2016) Masato Kato et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal conductivity measurement of (Pu1−xAmx)O2 (x=0.028, 0.072)

(2015) Taku Matsumoto et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Linear thermal expansion, thermal diffusivity and melting temperature of Am-MOX and Np-MOX

(2015) D. Prieur et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Impact of the cation distribution homogeneity on the americium oxidation state in the U 0.54 Pu 0.45 Am 0.01 O 2 − x mixed oxide

(2015) Romain Vauchy et al.   JOURNAL OF NUCLEAR MATERIALS

Modelling the thermal conductivity of (U x Th 1−x )O 2 and (U x Pu 1−x )O 2

(2015) M.W.D. Cooper et al.   JOURNAL OF NUCLEAR MATERIALS

The Thermodynamic Properties of thef-Elements and their Compounds. Part 2. The Lanthanide and Actinide Oxides

(2014) Rudy J. M. Konings et al.   JOURNAL OF PHYSICAL AND CHEMICAL REFERENCE DATA

Effect of Gd2O3Dispersion on the Thermal Conductivity of UO2

(2012) Kouta IWASAKI et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems

(2011) Christine Guéneau et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal conductivity of (U,Pu,Np)O2 solid solutions

(2009) Kyoichi Morimoto et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal conductivities of (U, Pu, Am)O2 solid solutions

(2007) Kyoichi Morimoto et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Solidus and liquidus of plutonium and uranium mixed oxide

(2007) Masato Kato et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Thermal conductivities of hypostoichiometric (U, Pu, Am)O2−x oxide

(2007) Kyoichi Morimoto et al.   JOURNAL OF NUCLEAR MATERIALS

Solidus and liquidus temperatures in the UO2–PuO2 system

(2007) M. Kato et al.   JOURNAL OF NUCLEAR MATERIALS