For an analysis of the oxidation behavior of UO2 nuclear fuel pellet under a loss of water coolant accident in a spent nuclear fuel pool of an LWR, thermodynamic assessments of UO2 oxidation were carried out under various atmospheric conditions. In a steam atmosphere, it was assessed that UO2 would not be fully oxidized into U3O8 due to the relatively lower oxygen partial pressure, while UO2 will be fully oxidized into U3O8 in an air atmosphere. In an air and steam mixture at-mosphere, the UO2 oxidation was dominantly affected by the air volumetric fraction, because of the relatively higher oxygen partial pressure of air. In addition, the effect of H2 volumetric fraction on the oxygen partial pressure under a mixture atmosphere was calculat...
The elemental and chemical composition of nuclear fuel pellets are key factors influencing the mater...
International audienceDuring dry air storage, the oxidation of the spent fuel in case of cladding an...
To assess the long-term leaching behaviour of UO2, the main constituent of spent nuclear fuel, the o...
Micro-plate or microcell UO2–Mo is considered a promising accident tolerant fuel candidate for water...
In this paper the results of laboratory tests on oxidation behavior of non-irradiated UO Studies of ...
The elemental and chemical composition of nuclear fuel pellets are key factors influencing the mater...
Results for the radial distribution of the oxygen potential and stoichiometry of a PWR fuel with an ...
Technical paper submitted for peer-review, accepted, and presented at the 2018 Topfuel conference (S...
International audienceThe analysis of the PHEBUS FPT0 and FPT1 tests and some VERCORS tests performe...
Spent nuclear fuel is composed of ≈95% UO2, and upon storage in geologic repository the fuel itse...
International audienceThe oxidation of sintered UO2 pellets and powder into U3O8 has been studied by...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...
Characterization of the fuel debris has been required for decommissioning Fukushima Daiichi Nuclear ...
Understanding the possible change in UO2 surface reactivity after exposure to oxidants is of key imp...
The volatility of UO/sub 2 plus or minus x/ and the phase relations in the uranium-oxygen system wer...
The elemental and chemical composition of nuclear fuel pellets are key factors influencing the mater...
International audienceDuring dry air storage, the oxidation of the spent fuel in case of cladding an...
To assess the long-term leaching behaviour of UO2, the main constituent of spent nuclear fuel, the o...
Micro-plate or microcell UO2–Mo is considered a promising accident tolerant fuel candidate for water...
In this paper the results of laboratory tests on oxidation behavior of non-irradiated UO Studies of ...
The elemental and chemical composition of nuclear fuel pellets are key factors influencing the mater...
Results for the radial distribution of the oxygen potential and stoichiometry of a PWR fuel with an ...
Technical paper submitted for peer-review, accepted, and presented at the 2018 Topfuel conference (S...
International audienceThe analysis of the PHEBUS FPT0 and FPT1 tests and some VERCORS tests performe...
Spent nuclear fuel is composed of ≈95% UO2, and upon storage in geologic repository the fuel itse...
International audienceThe oxidation of sintered UO2 pellets and powder into U3O8 has been studied by...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...
Characterization of the fuel debris has been required for decommissioning Fukushima Daiichi Nuclear ...
Understanding the possible change in UO2 surface reactivity after exposure to oxidants is of key imp...
The volatility of UO/sub 2 plus or minus x/ and the phase relations in the uranium-oxygen system wer...
The elemental and chemical composition of nuclear fuel pellets are key factors influencing the mater...
International audienceDuring dry air storage, the oxidation of the spent fuel in case of cladding an...
To assess the long-term leaching behaviour of UO2, the main constituent of spent nuclear fuel, the o...