From the present report 'Untersuchungen zur Radionuklidfreisetzung und zum Korrosionsverhalten von bestrahltem Kernbrennstoff aus Forschungsreaktoren unter Endlagerbedingungen' with the code number FKZ 9108 carried out in the time periode 01.06.1998 till 30.11.2001 the following results can be withdrawn: U/Al-RR-fuel elements corroded slowly in granite water (Grimsel-West) at 90 C under anaerobic conditions. For a complete dissolution of the fuel element a time period of 10"3 years is assumed according to present conservative results. In salt brines, especially in magnesium chloride rich brines the corrosion rate is high. Addition of GGG40 (basic material of the fuel element container with iron as main element) had an acceleration effe...
Reducing the uncertainties associated with the extrapolation to very long term of corrosion data and...
Experimente zur Korrosion von simulierten radioaktiven Abfallglaesern R7T7 in drei repraesentativen ...
One back-end option for spent HTR fuel elements proposed for future HTR fuel cycles in the EC is an ...
In order to assess the safety of the direct disposal of spent fuel, the corrosion resistance of the ...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
The discussion of a national fuel management concept for research reactor fuel elements is the reaso...
Im Rahmen der Diskussion eines nationalen Entsorgungskonzepts mit direkter Endlagerung von Forschung...
In previous corrosion studies, carbon steels and the alloy Ti 99.8-Pd were identified as promising m...
On the basis of the political decision that there should be no reprocessing of spent research reacto...
In order to determine the long-term performance of spent fuel during direct disposal, high burnup fu...
For the assessment of a confident und sustainable final disposal of high level radioactive waste –fu...
Bei der Endlagerung radioaktiver Abfaelle in einem Salzstock kann durch anaerobe Korrosion der metal...
Ein Ziel dieser Arbeit war es, die Bildung sowie die Langzeitstabilitaet von Sekundaerphasen zu unte...
Radionuclide source terms are derived for different disposal options of a potential final repository...
Four original, spent fuel elements of the type uranium/thorium oxide with a burnup of 17% fima have ...
Reducing the uncertainties associated with the extrapolation to very long term of corrosion data and...
Experimente zur Korrosion von simulierten radioaktiven Abfallglaesern R7T7 in drei repraesentativen ...
One back-end option for spent HTR fuel elements proposed for future HTR fuel cycles in the EC is an ...
In order to assess the safety of the direct disposal of spent fuel, the corrosion resistance of the ...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
The discussion of a national fuel management concept for research reactor fuel elements is the reaso...
Im Rahmen der Diskussion eines nationalen Entsorgungskonzepts mit direkter Endlagerung von Forschung...
In previous corrosion studies, carbon steels and the alloy Ti 99.8-Pd were identified as promising m...
On the basis of the political decision that there should be no reprocessing of spent research reacto...
In order to determine the long-term performance of spent fuel during direct disposal, high burnup fu...
For the assessment of a confident und sustainable final disposal of high level radioactive waste –fu...
Bei der Endlagerung radioaktiver Abfaelle in einem Salzstock kann durch anaerobe Korrosion der metal...
Ein Ziel dieser Arbeit war es, die Bildung sowie die Langzeitstabilitaet von Sekundaerphasen zu unte...
Radionuclide source terms are derived for different disposal options of a potential final repository...
Four original, spent fuel elements of the type uranium/thorium oxide with a burnup of 17% fima have ...
Reducing the uncertainties associated with the extrapolation to very long term of corrosion data and...
Experimente zur Korrosion von simulierten radioaktiven Abfallglaesern R7T7 in drei repraesentativen ...
One back-end option for spent HTR fuel elements proposed for future HTR fuel cycles in the EC is an ...