The aim of this study was to compare the leaching behaviour of irradiated UO2 and MOX and non-irradiated UO2 and SIM-FUEL. Direct comparisons using the very large amount of experimental data available in the literature are often difficult, not only because of the differences existing between SIMFUEL or non-irradiated UO2 and spent fuel (i.e. the presence of intense radiation fields surrounding irradiated fuel, hence radiolysis effects, or the formation of cracks and pores due to the volatile fission products, hence larger surface area), but also because of different experimental procedures used by different authors. In the case of MOX, the possible effects due to the different initial composition and microstructure also affect the leaching ...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
The dissolution behavior of an unirradiated chemical analogue of spent nuclear fuel (SIMFUEL) has be...
The aim of this work was to study the separate effect of fission fragment damage on the dissolution ...
This presentation will provide an overview on recent studies on spent nuclear fuel behaviour under d...
International audienceFew studies exist concerning the alteration of Mimas Mixed-OXide (MOX) fuel, a...
In the context of spent nuclear fuel (SNF) disposition, a deep geological repository (DGR) based on ...
International audienceFor underwater interim storage of spent UOX fuel assemblies it is necessary to...
The leaching of a high-burn-up spent nuclear fuel (48 MWd/KgU) has been studied in a carbonate-conta...
International audienceThe aim of this work was to study the separate effect of fission fragment dama...
Assessing the performance of Spent (or Used) Nuclear Fuel (UNF) in geological repository requires qu...
In order to assess the impact of α-radiolysis of water on the oxidative dissolution of spent fuel, a...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
Leaching experiments were performed on UO2 pellets doped with alpha-emitters (Pu-238/239) and on spe...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
The dissolution behavior of an unirradiated chemical analogue of spent nuclear fuel (SIMFUEL) has be...
The aim of this work was to study the separate effect of fission fragment damage on the dissolution ...
This presentation will provide an overview on recent studies on spent nuclear fuel behaviour under d...
International audienceFew studies exist concerning the alteration of Mimas Mixed-OXide (MOX) fuel, a...
In the context of spent nuclear fuel (SNF) disposition, a deep geological repository (DGR) based on ...
International audienceFor underwater interim storage of spent UOX fuel assemblies it is necessary to...
The leaching of a high-burn-up spent nuclear fuel (48 MWd/KgU) has been studied in a carbonate-conta...
International audienceThe aim of this work was to study the separate effect of fission fragment dama...
Assessing the performance of Spent (or Used) Nuclear Fuel (UNF) in geological repository requires qu...
In order to assess the impact of α-radiolysis of water on the oxidative dissolution of spent fuel, a...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
Leaching experiments were performed on UO2 pellets doped with alpha-emitters (Pu-238/239) and on spe...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
The dissolution behavior of an unirradiated chemical analogue of spent nuclear fuel (SIMFUEL) has be...
The aim of this work was to study the separate effect of fission fragment damage on the dissolution ...