The grouped actinide extraction (GANEX) process combines two extractants CyMe4-BTBP and TBP in a diluent, in this study phenyl trifluoromethyl sulfone (FS-13). The extraction of U-235, Np-239, Pu-238, Am-241, Cm-244 and Eu-152 has been investigated in four different systems. System 1: 70 %vol FS-13, 30 %vol TBP and 10 mM CyMe4-BTBP, system 2: 70 %vol FS-13 and 30 %vol TBP, system 3: 100 %vol FS-13 and 10 mM CyMe4-BTBP and system 4: pure FS-13. In all cases 4 M HNO3 was used as aqueous phase. In system 1 all actinides were extracted and separated from the lanthanides. In both system 2 and 3 mainly U and Pu were extracted. In system 4 none of the metals were extracted
Two Group ActiNide EXtraction solvents for the extraction of actinides from used nuclear fuel for tr...
Studies have been performed with the purpose of determining the optimal solvent composition of a Cha...
Within the framework of our research activities related to the partitioning of spent nuclear-fuel so...
The grouped actinide extraction (GANEX) process combines two extractants CyMe4-BTBP and TBP in a dil...
A Grouped ActiNide EXtraction (GANEX) process for the extraction of actinides from used nuclear fuel...
The demand for electricity and electrical energy is very high both in Sweden and in the other indust...
Several solvents for Grouped ActiNide EXtraction (GANEX) processes have been investigated at Chalmer...
Several solvents for Grouped ActiNide EXtraction (GANEX) processes have been investigated at Chalmer...
A group actinide extraction process (GANEX) for reprocessing of used nuclear fuel has earlier been p...
A newly developed method for advanced reprocessing of used nuclear fuel is the Group ActiNide EXtrac...
In this work, stability experiments have been performed on a phenyl trifluoromethyl sulfone based so...
Used nuclear fuel taken directly from a reactor is radiotoxic for mankind and its environment for a ...
When uranium is used as fuel in nuclear reactors it both undergoes neutron induced fission as well a...
A Group ActiNide EXtraction (GANEX) separation system for transmutation has been developed, combinin...
Research focus within separation for transmutation in Europe today lies in the development of a solv...
Two Group ActiNide EXtraction solvents for the extraction of actinides from used nuclear fuel for tr...
Studies have been performed with the purpose of determining the optimal solvent composition of a Cha...
Within the framework of our research activities related to the partitioning of spent nuclear-fuel so...
The grouped actinide extraction (GANEX) process combines two extractants CyMe4-BTBP and TBP in a dil...
A Grouped ActiNide EXtraction (GANEX) process for the extraction of actinides from used nuclear fuel...
The demand for electricity and electrical energy is very high both in Sweden and in the other indust...
Several solvents for Grouped ActiNide EXtraction (GANEX) processes have been investigated at Chalmer...
Several solvents for Grouped ActiNide EXtraction (GANEX) processes have been investigated at Chalmer...
A group actinide extraction process (GANEX) for reprocessing of used nuclear fuel has earlier been p...
A newly developed method for advanced reprocessing of used nuclear fuel is the Group ActiNide EXtrac...
In this work, stability experiments have been performed on a phenyl trifluoromethyl sulfone based so...
Used nuclear fuel taken directly from a reactor is radiotoxic for mankind and its environment for a ...
When uranium is used as fuel in nuclear reactors it both undergoes neutron induced fission as well a...
A Group ActiNide EXtraction (GANEX) separation system for transmutation has been developed, combinin...
Research focus within separation for transmutation in Europe today lies in the development of a solv...
Two Group ActiNide EXtraction solvents for the extraction of actinides from used nuclear fuel for tr...
Studies have been performed with the purpose of determining the optimal solvent composition of a Cha...
Within the framework of our research activities related to the partitioning of spent nuclear-fuel so...