On the basis of the political decision that there should be no reprocessing of spent research reactor fuel elements (RR-FE) in Germany, direct disposal in deep geological formations is under discussion. The RR-FE are classified as heat-generating high-level radioactive waste and their disposal is aspired preferential in salt formations. A possible accident scenario for long-term safety analysis in a salt repository is a water ingress, whereby highly concentrated salt brines will arise. Leaching experiments with irradiated and unirradiated metallic UAl$_{x}$-Al- and uranium-silicide RR-FE in repository-relevant solutions, such as clay pore water (Mont-Terri-Type) or MgCl$_{2}$-rich salt brine (brine 2) were therefore undertaken at the instit...
During the reprocessing of spent Material Test Reactor (MTR) fuel elements from research reactor DID...
Radionuclide source terms are derived for different disposal options of a potential final repository...
From leaching experiments with metallic uranium-aluminum research reactor fuel elements in repositor...
For the assessment of a confident und sustainable final disposal of high level radioactive waste –fu...
Leaching experiments with metallic uranium-aluminum research-reactor fuel elements in repository-rel...
The corrosion of the UAl-Al research reactorfuel type in synthetic MgCl2-rich brine (static batch-ty...
Corrosion experiments with non-irradiated U3Si2-Al research reactor fuel samples were carried out in...
From the present report 'Untersuchungen zur Radionuklidfreisetzung und zum Korrosionsverhalten von b...
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...
In order to contribute to the long-term safety analysis of direct disposed research reactor fuel ele...
In previous corrosion studies, carbon steels and the alloy Ti 99.8-Pd were identified as promising m...
Layered doubled hydroxides (LDH), consisting of positively charged octahedral brucite-type layers an...
From leaching experiments with metallic uranium-aluminum research reactor fuel elements in repositor...
In order to assess the safety of the direct disposal of spent fuel, the corrosion resistance of the ...
During the reprocessing of spent Material Test Reactor (MTR) fuel elements from research reactor DID...
Radionuclide source terms are derived for different disposal options of a potential final repository...
From leaching experiments with metallic uranium-aluminum research reactor fuel elements in repositor...
For the assessment of a confident und sustainable final disposal of high level radioactive waste –fu...
Leaching experiments with metallic uranium-aluminum research-reactor fuel elements in repository-rel...
The corrosion of the UAl-Al research reactorfuel type in synthetic MgCl2-rich brine (static batch-ty...
Corrosion experiments with non-irradiated U3Si2-Al research reactor fuel samples were carried out in...
From the present report 'Untersuchungen zur Radionuklidfreisetzung und zum Korrosionsverhalten von b...
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...
In order to contribute to the long-term safety analysis of direct disposed research reactor fuel ele...
In previous corrosion studies, carbon steels and the alloy Ti 99.8-Pd were identified as promising m...
Layered doubled hydroxides (LDH), consisting of positively charged octahedral brucite-type layers an...
From leaching experiments with metallic uranium-aluminum research reactor fuel elements in repositor...
In order to assess the safety of the direct disposal of spent fuel, the corrosion resistance of the ...
During the reprocessing of spent Material Test Reactor (MTR) fuel elements from research reactor DID...
Radionuclide source terms are derived for different disposal options of a potential final repository...
From leaching experiments with metallic uranium-aluminum research reactor fuel elements in repositor...