The impact of burn-up on the instant release fraction (IRF) from spent fuel was studied using very high burn-up UO2 fuel (∼ 100 GWd/t) from a prototype high temperature reactor (HTR). TRISO (TRi-structural-ISO-tropic) particles from the spherical fuel elements contain UO2 fuel kernels (500 μm diameter) which are coated by three tight layers ensuring the encapsulation of fission products during reactor operation. After cracking of the tight coatings 85Kr and 14C as 14CO2 were detected in the gas fraction. Xe was not detected in the gas fraction, although ESEM (Environmental Scanning Electron Micoscope) investigations revealed an accumulation in the buffer. UO2 fuel kernels were exposed to synthetic groundwater under oxic and anoxic/reducing ...
In the context of spent nuclear fuel (SNF) disposition, a deep geological repository (DGR) based on ...
Corrosion of spent UO{sub 2} fuel has been studied in experiments conducted for nearly six years. Ox...
Two high-temperature reactors (AVR and THTR) operated in Germany have produced about 1 million spent...
Supported by results of calculations performed with two analytical tools (MFPR, which takes account ...
It is important to understand fission-product (FP) and kernel micro-structure evolution in TRISO-coa...
The leaching of a high-burn-up spent nuclear fuel (48 MWd/KgU) has been studied in a carbonate-conta...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
In the safety case for the geological disposal of nuclear waste, the release of radioactivity from t...
This presentation will provide an overview on recent studies on spent nuclear fuel behaviour under d...
The aim of this study was to compare the leaching behaviour of irradiated UO2 and MOX and non-irradi...
The instant release fraction of a spent nuclear fuel is a matter of concern in the performance asses...
Experiments are being conducted that examine the reaction of UO{sub 2} with dripping oxygenated grou...
A fission product and Pu rich porous structure forms at the radial periphery of LWR fuel pellet at a...
A BWR design UO2 fuel irradiated to a burnup of 7.9% FIMA was selected for a careful calculational a...
The safe disposal in a geological repository is proposed for the spent fuel elements obtained from o...
In the context of spent nuclear fuel (SNF) disposition, a deep geological repository (DGR) based on ...
Corrosion of spent UO{sub 2} fuel has been studied in experiments conducted for nearly six years. Ox...
Two high-temperature reactors (AVR and THTR) operated in Germany have produced about 1 million spent...
Supported by results of calculations performed with two analytical tools (MFPR, which takes account ...
It is important to understand fission-product (FP) and kernel micro-structure evolution in TRISO-coa...
The leaching of a high-burn-up spent nuclear fuel (48 MWd/KgU) has been studied in a carbonate-conta...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
In the safety case for the geological disposal of nuclear waste, the release of radioactivity from t...
This presentation will provide an overview on recent studies on spent nuclear fuel behaviour under d...
The aim of this study was to compare the leaching behaviour of irradiated UO2 and MOX and non-irradi...
The instant release fraction of a spent nuclear fuel is a matter of concern in the performance asses...
Experiments are being conducted that examine the reaction of UO{sub 2} with dripping oxygenated grou...
A fission product and Pu rich porous structure forms at the radial periphery of LWR fuel pellet at a...
A BWR design UO2 fuel irradiated to a burnup of 7.9% FIMA was selected for a careful calculational a...
The safe disposal in a geological repository is proposed for the spent fuel elements obtained from o...
In the context of spent nuclear fuel (SNF) disposition, a deep geological repository (DGR) based on ...
Corrosion of spent UO{sub 2} fuel has been studied in experiments conducted for nearly six years. Ox...
Two high-temperature reactors (AVR and THTR) operated in Germany have produced about 1 million spent...