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Arnal, Thierry; Cousinou, Gerard; Ganivet, Michel.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Developpement des Elements Combustibles1978
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Developpement des Elements Combustibles1978
AbstractAbstract
[en] A procedure is described for separating plutonium from a uranium VI and plutonium IV mixture contained in an organic phase (tributyl phosphate diluted in dodecane). This separation is obtained by extracting the plutonium III using two organic reducers: hydrazine and paraminophenol. Paraminophenol has excellent reducing qualities, similar to those of ferrous sulphamate, but has the added advantage of not contaminating extracted plutonium. This procedure is currently used in processing production wastes from mixed oxide (U,Pu)O2 fuels; the installation using this procedure is described in detail in this paper. Operating results show the remarkable efficiency of this procedure: the separated plutonium and uranium mass flows have been increased to 185 and 350 g.h-1 respectively; the uranium contains less than 0.1 ppm of plutonium on completion of the purification cycle
[fr]
On decrit un procede de separation du plutonium d'un melange d'uranium VI et de plutonium IV, contenu dans une phase organique (phosphate de tributyle dilue dans le dodecane). Cette separation est obtenue par reextraction du plutonium III au moyen de deux reducteurs organiques: hydrazine et para-aminophenol. Le para-aminophenol possede d'excellentes proprietes reductrices, semblables a celles du sulfamate ferreux, il presente l'avantage de ne pas polluer le plutonium reextrait. Ce procede trouve actuellement une application pratique dans le traitement des rebuts de fabrication des combustibles a base d'oxyde mixte (U,Pu)O2; l'installation qui le met en oeuvre fait l'objet d'une description detaillee dans cette note. Les resultats d'exploitation montrent l'efficacite remarquable du procede: les debits-masse de plutonium et d'uranium separes ont ete portes respectivement a 185 et 530 g.h-1; l'uranium contient moins de 0,1 ppm de plutonium a la sortie du cycle de purificationOriginal Title
Etude d'un procede de separation du plutonium par reextraction reductrice. Application au traitement des rebuts de fabrication des combustibles a base d'oxyde mixte (U,Pu)O2
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Nov 1978; 34 p
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Report
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ACTINIDE COMPOUNDS, ALKANES, AROMATICS, BUTYL PHOSPHATES, CHARGED PARTICLES, CHEMICAL REACTIONS, DATA, DATA FORMS, ESTERS, EXTRACTION APPARATUSES, HYDROCARBONS, HYDROGEN COMPOUNDS, HYDROXY COMPOUNDS, INFORMATION, INORGANIC ACIDS, IONS, NITROGEN COMPOUNDS, NUMERICAL DATA, ORGANIC COMPOUNDS, ORGANIC PHOSPHORUS COMPOUNDS, OXYGEN COMPOUNDS, PHOSPHORIC ACID ESTERS, SEPARATION PROCESSES, TRANSURANIUM COMPOUNDS
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