The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigated by means of leach tests. The samples covered PWR and BWR fuels at average rod burn-up in the range of 45–63 GWd/tHM and included clad fuel segments, fuel segments with opened cladding, fuel fragments and fuel powder. The tests were performed with sodium chloride – bicarbonate solutions under oxidizing conditions and, for one test, in reducing Ar/H2 atmosphere. The iodine and cesium release could be partially explained by the differences in sample preparation, leading to different sizes and properties of the exposed surface areas. Iodine and cesium releases tend to correlate with FGR and linear power rating, but the scatter of the data is si...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
Fission product (FP) and actinide release behaviour from degraded fuel in the VERCORS RT7, HT2 and H...
This report describes the application of a vapor transportation model to fission product release dat...
During reactor operation the fission gases Kr and Xe are formed within the UO2 matrix of nuclear fue...
Three tests have provided additional data on fission product release under LWR accident conditions i...
The leaching of a high-burn-up spent nuclear fuel (48 GWd/tU) has been studied in a carbonate-contai...
Experiments in the controlled melting of irradiated fuel speciman, particularly of the APPR, STR, an...
The experiments Phébus FP FPT-0 to FPT-3 tests conducted by IRSN have produced a large quantity of d...
The instant release fraction of a spent nuclear fuel is a matter of concern in the performance asses...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
A series of fuel behavior experiments are being conducted in the Heavy Boiling Water Reactor in Hald...
A commercial PWR fuel sample with a local burn-up of about 240 MWd/kgHM was annealed in a Knudsen ce...
The aim of this study was to compare the leaching behaviour of irradiated UO2 and MOX and non-irradi...
The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercise...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
Fission product (FP) and actinide release behaviour from degraded fuel in the VERCORS RT7, HT2 and H...
This report describes the application of a vapor transportation model to fission product release dat...
During reactor operation the fission gases Kr and Xe are formed within the UO2 matrix of nuclear fue...
Three tests have provided additional data on fission product release under LWR accident conditions i...
The leaching of a high-burn-up spent nuclear fuel (48 GWd/tU) has been studied in a carbonate-contai...
Experiments in the controlled melting of irradiated fuel speciman, particularly of the APPR, STR, an...
The experiments Phébus FP FPT-0 to FPT-3 tests conducted by IRSN have produced a large quantity of d...
The instant release fraction of a spent nuclear fuel is a matter of concern in the performance asses...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
A series of fuel behavior experiments are being conducted in the Heavy Boiling Water Reactor in Hald...
A commercial PWR fuel sample with a local burn-up of about 240 MWd/kgHM was annealed in a Knudsen ce...
The aim of this study was to compare the leaching behaviour of irradiated UO2 and MOX and non-irradi...
The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercise...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
Fission product (FP) and actinide release behaviour from degraded fuel in the VERCORS RT7, HT2 and H...
This report describes the application of a vapor transportation model to fission product release dat...