International audienceThe behaviour of stoichiometric U1−yPuyO2 compounds used as nuclear fuel is relatively well understood. Conversely, the effects of stoichiometry deviation on fuel performance and fuel stability are intricate and poorly studied. In order to investigate what affect these have on the thermophysical properties of hypo-stoichiometric U1−yPuyO2−x mixed oxide fuel, new interaction parameters based on the many-body CRG (Cooper–Rushton–Grimes) potential formalism were optimized. The new potential has been fitted to match experimental lattice parameters of U0.70Pu0.30O1.99 (O/M = 1.99) and U0.70Pu0.30O1.97 (O/M = 1.97), where M represents the total amount of metallic cations, through a rigorous procedure combining classical mole...
International audienceThe ternary thermodynamic U–Pu–O system has been studied for decades for MOX f...
The physical properties of uranium dioxide vary greatly with stoichiometry. Oxidation towards hypers...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
International audienceThe molecular Monte Carlo method, combined with the CRG interatomic potential,...
Fundamental understanding of the behaviour of nuclear fuel has been of great importance. Enhancing t...
International audienceThe fuel of civil nuclear plants, UO2, melts at 3120 K. During an hypothetical...
International audienceWe assess five empirical interatomic potentials in the approximation of rigid ...
A first principles thermodynamic model for nuclear fuel is in an advanced stage of development. This...
We extend our recently developed interatomic potentials for UO_2 to the fuel system (U,Pu,Np)O_2. We...
Our series of articles is devoted to high-precision molecular dynamics simulation of mixed actinide-...
International audienceAmericium is a chemical element produced by neutron capture in nuclear reactor...
International audienceOne way of increasing significantly the efficiency in designing and qualifying...
Uranium dioxide (UO₂) is the most commonly used fuel in light-water nuclear reactors and thermal con...
Atomistic Simulation techniques have been used to model surface and bulk properties of UO_2, the mos...
Spent nuclear fuel from commercial reactors is comprised of 95-99 percent UO{sub 2} and 1-5 percent ...
International audienceThe ternary thermodynamic U–Pu–O system has been studied for decades for MOX f...
The physical properties of uranium dioxide vary greatly with stoichiometry. Oxidation towards hypers...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
International audienceThe molecular Monte Carlo method, combined with the CRG interatomic potential,...
Fundamental understanding of the behaviour of nuclear fuel has been of great importance. Enhancing t...
International audienceThe fuel of civil nuclear plants, UO2, melts at 3120 K. During an hypothetical...
International audienceWe assess five empirical interatomic potentials in the approximation of rigid ...
A first principles thermodynamic model for nuclear fuel is in an advanced stage of development. This...
We extend our recently developed interatomic potentials for UO_2 to the fuel system (U,Pu,Np)O_2. We...
Our series of articles is devoted to high-precision molecular dynamics simulation of mixed actinide-...
International audienceAmericium is a chemical element produced by neutron capture in nuclear reactor...
International audienceOne way of increasing significantly the efficiency in designing and qualifying...
Uranium dioxide (UO₂) is the most commonly used fuel in light-water nuclear reactors and thermal con...
Atomistic Simulation techniques have been used to model surface and bulk properties of UO_2, the mos...
Spent nuclear fuel from commercial reactors is comprised of 95-99 percent UO{sub 2} and 1-5 percent ...
International audienceThe ternary thermodynamic U–Pu–O system has been studied for decades for MOX f...
The physical properties of uranium dioxide vary greatly with stoichiometry. Oxidation towards hypers...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...