AbstractFour separation methods were developed for performance control of hydrometallurgical extraction processes as COEX™ or advanced PUREX. These methods used implemented the operations of radionuclides oxidation state adjustment and chromatographic separation using TEVA resin. Concerning FP raffinate, the method consisted in reducing Np traces to the valence IV by a mixture of ferrous sulfamate and ascorbic acid, to fix Np(IV) on “TEVA” resin and to eluate it by a nitrohydrofluoric acid solution. The Np recovery yield is 100%. The decontamination of Np is sufficiently high to allow its analysis by FXL (Zr/Np < 1). The study also showed that in presence of Zr and Tc, Pu behaved like Np. The mixture of ferrous sulfamate and ascorbic acid h...
Experimental investigations to determine fission product decontamination factors while employing the...
Experimental investigations to determine fission product decontamination factors while employing the...
AbstractIn the PUREX process, the first U-Pu purification cycle (1CUPu) is not efficient enough for ...
AbstractFour separation methods were developed for performance control of hydrometallurgical extract...
In nuclear reprocessing, PUREX, a solvent extraction process, has long been the separation method em...
AbstractTo support the development of an Advanced PUREX process that fully recovers neptunium with u...
The classical process to recover uranium (U) and plutonium (Pu) from used nuclear fuel using tributy...
AbstractA simple and rapid spectrophotometric method has been developed to enable the determination ...
Closing the Th-U fuel cycle, the recovered material should be purified from Np and Pu in the course ...
The classical process to recover uranium (U) and plutonium (Pu) from used nuclear fuel using tributy...
Although actinides are the most informative elements with respect to the nature of a nuclear acciden...
International audienceIn the back-end of nuclear fuel cycle, liquid-liquid extraction processes basi...
International audienceIn the back-end of nuclear fuel cycle, liquid-liquid extraction processes basi...
A possibility of standarizing the extraction-behavior of Neptunium during the reprocessing of spent ...
Recycling of actinides from spent nuclear fuel by their selective separation followed by transmutati...
Experimental investigations to determine fission product decontamination factors while employing the...
Experimental investigations to determine fission product decontamination factors while employing the...
AbstractIn the PUREX process, the first U-Pu purification cycle (1CUPu) is not efficient enough for ...
AbstractFour separation methods were developed for performance control of hydrometallurgical extract...
In nuclear reprocessing, PUREX, a solvent extraction process, has long been the separation method em...
AbstractTo support the development of an Advanced PUREX process that fully recovers neptunium with u...
The classical process to recover uranium (U) and plutonium (Pu) from used nuclear fuel using tributy...
AbstractA simple and rapid spectrophotometric method has been developed to enable the determination ...
Closing the Th-U fuel cycle, the recovered material should be purified from Np and Pu in the course ...
The classical process to recover uranium (U) and plutonium (Pu) from used nuclear fuel using tributy...
Although actinides are the most informative elements with respect to the nature of a nuclear acciden...
International audienceIn the back-end of nuclear fuel cycle, liquid-liquid extraction processes basi...
International audienceIn the back-end of nuclear fuel cycle, liquid-liquid extraction processes basi...
A possibility of standarizing the extraction-behavior of Neptunium during the reprocessing of spent ...
Recycling of actinides from spent nuclear fuel by their selective separation followed by transmutati...
Experimental investigations to determine fission product decontamination factors while employing the...
Experimental investigations to determine fission product decontamination factors while employing the...
AbstractIn the PUREX process, the first U-Pu purification cycle (1CUPu) is not efficient enough for ...