AbstractIn the PUREX process, the first U-Pu purification cycle (1CUPu) is not efficient enough for the decontamination of uranium flow out of neptunium. In this context, molecules known for their strong complexing power for actinides(IV) in aqueous phase, such as acetohydroxamic acid (AHA) have been tested in batch experiments to strip Np and Pu from TBP solvent loaded with U. A phenomenological model was developed and with the help of this model, a flowsheet of a counter-current alpha barrier process was designed and tested in C17 glove boxes in ATALANTE facility. A decontamination factor DFU/Np of 480 was obtained, higher than DFU/Np required by UNIREP standards
Graduation date: 2011Used Nuclear Fuel (UNF) contains transuranic (TRU) elements and numerous fissio...
The speciation of hexavalent U and tetravalent Pu will be examined in the TBP-dodecane- nitric acid ...
Two full continuous countercurrent processes for the recovery of trivalent actinides (An(III)) from ...
AbstractIn the PUREX process, the first U-Pu purification cycle (1CUPu) is not efficient enough for ...
AbstractTo support the development of an Advanced PUREX process that fully recovers neptunium with u...
Simple hydroxamic acids such as acteohydroxamic acid (AHA) have been identified as suitable reagents...
Hydroxamic acids are promising complexant based alternatives to the reductant (U4+ or Fe2+) based se...
Simple Hydroxamic acids (XHAs) are salt free, organic compounds with affinities for hard cations suc...
AbstractFour separation methods were developed for performance control of hydrometallurgical extract...
AbstractA brief status of the development of actinide separation in china is presented. The activiti...
Routing neptunium to a single product in spent nuclear fuel reprocessing is a significant challenge....
In order to recycle potentially valuable uranium and plutonium, the Purex process has been successfu...
The classical process to recover uranium (U) and plutonium (Pu) from used nuclear fuel using tributy...
The objective of this thesis is to contribute for design and operation of Purex process, which is ad...
The classical process to recover uranium (U) and plutonium (Pu) from used nuclear fuel using tributy...
Graduation date: 2011Used Nuclear Fuel (UNF) contains transuranic (TRU) elements and numerous fissio...
The speciation of hexavalent U and tetravalent Pu will be examined in the TBP-dodecane- nitric acid ...
Two full continuous countercurrent processes for the recovery of trivalent actinides (An(III)) from ...
AbstractIn the PUREX process, the first U-Pu purification cycle (1CUPu) is not efficient enough for ...
AbstractTo support the development of an Advanced PUREX process that fully recovers neptunium with u...
Simple hydroxamic acids such as acteohydroxamic acid (AHA) have been identified as suitable reagents...
Hydroxamic acids are promising complexant based alternatives to the reductant (U4+ or Fe2+) based se...
Simple Hydroxamic acids (XHAs) are salt free, organic compounds with affinities for hard cations suc...
AbstractFour separation methods were developed for performance control of hydrometallurgical extract...
AbstractA brief status of the development of actinide separation in china is presented. The activiti...
Routing neptunium to a single product in spent nuclear fuel reprocessing is a significant challenge....
In order to recycle potentially valuable uranium and plutonium, the Purex process has been successfu...
The classical process to recover uranium (U) and plutonium (Pu) from used nuclear fuel using tributy...
The objective of this thesis is to contribute for design and operation of Purex process, which is ad...
The classical process to recover uranium (U) and plutonium (Pu) from used nuclear fuel using tributy...
Graduation date: 2011Used Nuclear Fuel (UNF) contains transuranic (TRU) elements and numerous fissio...
The speciation of hexavalent U and tetravalent Pu will be examined in the TBP-dodecane- nitric acid ...
Two full continuous countercurrent processes for the recovery of trivalent actinides (An(III)) from ...