The Office of Science, Basic Energy Sciences, has funded the INL as one of the Energy Frontier Research Centers in the area of material science of nuclear fuels. This document is the required annual report to the Office of Science that outlines the accomplishments for the period of May 2010 through April 2011. The aim of the Center for Material Science of Nuclear Fuels (CMSNF) is to establish the foundation for predictive understanding of the effects of irradiation-induced defects on thermal transport in oxide nuclear fuels. The science driver of the center’s investigation is to understand how complex defect and microstructures affect phonon mediated thermal transport in UO2, and achieve this understanding for the particular case of irradia...
International audienceMechanical properties of nuclear fuel are a complex problem, involving many co...
International audienceNuclear fuel plays a fundamental role in the design of innovative nuclear syst...
A wide range of materials are currently under consideration for use in advanced nuclear fuel cycle a...
The thermophysical properties of nuclear fuels being developed in generation IV nuclear reactors are...
International audienceFuel behaviour under irradiation is extremely complex due to the combined effe...
Uranium, a common element that can be found across the world, can be used in nuclear reactors as UO2...
We report experiments to determine the effect of radiation damage on the phonon spectra of the most ...
Uranium dioxide (UO₂) is the most commonly used fuel in light-water nuclear reactors and thermal con...
Nuclear fuel performance is deteriorated due to radiation defects. Therefore, to investigate the eff...
Lattice vibration is the main microscopic mechanism for thermal transport in dielectric materials. T...
Thermal conductivity measurements have been carried out between 80 mK and 30 K in quartz after γ, el...
International audienceThe nuclear oxide fuels are submitted ‘in-pile’ to strong structural and chemi...
The knowledge of the thermal conductivity of nuclear fuel and its evolution as a function of tempera...
Graduation date: 2016The Boltzmann transport equation derived in the Self-Adjoint Angular Flux (SAAF...
Accurately predicting changes in the thermal conductivity of light water reactor UO2 fuel throughout...
International audienceMechanical properties of nuclear fuel are a complex problem, involving many co...
International audienceNuclear fuel plays a fundamental role in the design of innovative nuclear syst...
A wide range of materials are currently under consideration for use in advanced nuclear fuel cycle a...
The thermophysical properties of nuclear fuels being developed in generation IV nuclear reactors are...
International audienceFuel behaviour under irradiation is extremely complex due to the combined effe...
Uranium, a common element that can be found across the world, can be used in nuclear reactors as UO2...
We report experiments to determine the effect of radiation damage on the phonon spectra of the most ...
Uranium dioxide (UO₂) is the most commonly used fuel in light-water nuclear reactors and thermal con...
Nuclear fuel performance is deteriorated due to radiation defects. Therefore, to investigate the eff...
Lattice vibration is the main microscopic mechanism for thermal transport in dielectric materials. T...
Thermal conductivity measurements have been carried out between 80 mK and 30 K in quartz after γ, el...
International audienceThe nuclear oxide fuels are submitted ‘in-pile’ to strong structural and chemi...
The knowledge of the thermal conductivity of nuclear fuel and its evolution as a function of tempera...
Graduation date: 2016The Boltzmann transport equation derived in the Self-Adjoint Angular Flux (SAAF...
Accurately predicting changes in the thermal conductivity of light water reactor UO2 fuel throughout...
International audienceMechanical properties of nuclear fuel are a complex problem, involving many co...
International audienceNuclear fuel plays a fundamental role in the design of innovative nuclear syst...
A wide range of materials are currently under consideration for use in advanced nuclear fuel cycle a...