For the assessment of a confident und sustainable final disposal of high level radioactive waste –fuel elements of german research reactors also account for such waste – in suitable, deep geological facilities, processes of the alteration of the disposed of waste and therefore the formation of the corrosion products, i. e. secondary phases must be well understood considering an accident scenario of a potential water inflow. In order to obtain secondary phases non-irradiated research reactor fuel elements (FR-BE) consisting of UAl$_{x}$-Al were subjected to magnesium chloride rich brine (brine 2, salt repository) and to clay pore solution, respectively and furthermore of the type U$_{3}$Si$_{2}$-Al were solely subjected to magnesium chloride...
Introduction The Belgian Reactor 1 (BR1) fuel is composed of natural unalloyed metallic uranium, coa...
Deep geological disposal of high level nuclearwaste, such as spent nuclear fuel is being considered ...
One back-end option for spent HTR fuel elements proposed for future HTR fuel cycles in the EC is an ...
Corrosion experiments with non-irradiated U3Si2-Al research reactor fuel samples were carried out in...
The corrosion of the UAl-Al research reactorfuel type in synthetic MgCl2-rich brine (static batch-ty...
On the basis of the political decision that there should be no reprocessing of spent research reacto...
Corrosion experiments with non-irradiated uranium-aluminium fuel elements were performed in MgCl2-ri...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
From the present report 'Untersuchungen zur Radionuklidfreisetzung und zum Korrosionsverhalten von b...
The discussion of a national fuel management concept for research reactor fuel elements is the reaso...
The reactors of the next generation proposed as part of the Gen IV Initiative also include a reactor...
In order to assess the safety of the direct disposal of spent fuel, the corrosion resistance of the ...
The purpose of this analysis/model report (AMR) is to assess the potential for uranium (U) (VI) comp...
During the reprocessing of spent Material Test Reactor (MTR) fuel elements from research reactor DID...
Two steps of a pyrochemical route for the recovery of actinides from spent metallic nuclear fuel are...
Introduction The Belgian Reactor 1 (BR1) fuel is composed of natural unalloyed metallic uranium, coa...
Deep geological disposal of high level nuclearwaste, such as spent nuclear fuel is being considered ...
One back-end option for spent HTR fuel elements proposed for future HTR fuel cycles in the EC is an ...
Corrosion experiments with non-irradiated U3Si2-Al research reactor fuel samples were carried out in...
The corrosion of the UAl-Al research reactorfuel type in synthetic MgCl2-rich brine (static batch-ty...
On the basis of the political decision that there should be no reprocessing of spent research reacto...
Corrosion experiments with non-irradiated uranium-aluminium fuel elements were performed in MgCl2-ri...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
From the present report 'Untersuchungen zur Radionuklidfreisetzung und zum Korrosionsverhalten von b...
The discussion of a national fuel management concept for research reactor fuel elements is the reaso...
The reactors of the next generation proposed as part of the Gen IV Initiative also include a reactor...
In order to assess the safety of the direct disposal of spent fuel, the corrosion resistance of the ...
The purpose of this analysis/model report (AMR) is to assess the potential for uranium (U) (VI) comp...
During the reprocessing of spent Material Test Reactor (MTR) fuel elements from research reactor DID...
Two steps of a pyrochemical route for the recovery of actinides from spent metallic nuclear fuel are...
Introduction The Belgian Reactor 1 (BR1) fuel is composed of natural unalloyed metallic uranium, coa...
Deep geological disposal of high level nuclearwaste, such as spent nuclear fuel is being considered ...
One back-end option for spent HTR fuel elements proposed for future HTR fuel cycles in the EC is an ...