Technical paper submitted for peer-review, accepted, and presented at the 2018 Topfuel conference (September 30 - October 04, 2018). The conference was held in Prague, Czech Republic. ---Abstract--- One of the problems for which currently no quantitative answer can be given, are the degradation kinetics of spent nuclear fuel under different atmospheres. In the present contribution, we report on preliminary results after low-temperature moisturized atmosphere oxidation of UO2, and the results are compared to recent results of dry air oxidation. The first results indicate that the addition of moisture results in a slight moderation of the oxidation reaction, when compared to dry oxidizing conditions
The storage behaviour of uranium dioxide powder is reviewed. Topics covered include the amount of ox...
Investigation of the interactions of plutonium dioxide with water vapor and with an oxygen-hydrogen ...
The kinetic and crystalline evolutions of UO2 during its oxidation into U3O8 at 250 degrees C in air...
For an analysis of the oxidation behavior of UO2 nuclear fuel pellet under a loss of water coolant a...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...
Abstract The management of Spent Nuclear Fuel (SNF) comprises different stages in which security is ...
Experiments have been conducted by Pacific Northwest National Laboratory to determine the oxidation ...
Oxidation tests in dry air were conducted on four LWR spent fuels at 175{degrees} and 195{degrees}C ...
Spent nuclear fuel is composed of ≈95% UO2, and upon storage in geologic repository the fuel itse...
International audienceDuring dry air storage, the oxidation of the spent fuel in case of cladding an...
The oxidation behavior of hydride-bearing corrosion products from uranium metal ZPPR fuel plates was...
In this paper the results of laboratory tests on oxidation behavior of non-irradiated UO Studies of ...
International audienceThe analysis of the PHEBUS FPT0 and FPT1 tests and some VERCORS tests performe...
Oxidation testing of K Basin-stored N Reactor fuel in dry air, moist air, and moist helium provided ...
International audienceAs part of a long-lasting dry storage, the oxidation of the spent fuel linked ...
The storage behaviour of uranium dioxide powder is reviewed. Topics covered include the amount of ox...
Investigation of the interactions of plutonium dioxide with water vapor and with an oxygen-hydrogen ...
The kinetic and crystalline evolutions of UO2 during its oxidation into U3O8 at 250 degrees C in air...
For an analysis of the oxidation behavior of UO2 nuclear fuel pellet under a loss of water coolant a...
Globally the most used nuclear fuel material is uranium(IV) oxide (UO2) and it is produced by powder...
Abstract The management of Spent Nuclear Fuel (SNF) comprises different stages in which security is ...
Experiments have been conducted by Pacific Northwest National Laboratory to determine the oxidation ...
Oxidation tests in dry air were conducted on four LWR spent fuels at 175{degrees} and 195{degrees}C ...
Spent nuclear fuel is composed of ≈95% UO2, and upon storage in geologic repository the fuel itse...
International audienceDuring dry air storage, the oxidation of the spent fuel in case of cladding an...
The oxidation behavior of hydride-bearing corrosion products from uranium metal ZPPR fuel plates was...
In this paper the results of laboratory tests on oxidation behavior of non-irradiated UO Studies of ...
International audienceThe analysis of the PHEBUS FPT0 and FPT1 tests and some VERCORS tests performe...
Oxidation testing of K Basin-stored N Reactor fuel in dry air, moist air, and moist helium provided ...
International audienceAs part of a long-lasting dry storage, the oxidation of the spent fuel linked ...
The storage behaviour of uranium dioxide powder is reviewed. Topics covered include the amount of ox...
Investigation of the interactions of plutonium dioxide with water vapor and with an oxygen-hydrogen ...
The kinetic and crystalline evolutions of UO2 during its oxidation into U3O8 at 250 degrees C in air...