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Titre du document / Document title

Promising pyrochemical actinide/lanthanide separation processes using aluminum

Auteur(s) / Author(s)

CONOCAR Olivier (1) ; DOUYERE Nicolas (1) ; GLATZ Jean-Paul (2) ; LACQUEMENT Jérome (1) ; MALMBECK Rikard (2) ; SERP Jérome (2) ;

Affiliation(s) du ou des auteurs / Author(s) Affiliation(s)

(1) Commissariat à l'Energie Atomique, Valrhô-Marcoule, DEN/DRCP/SCPS/LPP Bât. 399, BP17171, 30207 Bagnols-sur-Cèze, FRANCE
(2) European Commission, Joint Research Centre, Institute for Transuranium Elements P.O. Box 2340, 76125, Karlsruhe, ALLEMAGNE

Résumé / Abstract

Thermodynamic calculations have shown that aluminum is the most promising metallic solvent or support for the separation ofactinides (An) from lanthanides (Ln). In molten fluoride salt, the technique of reductive extraction is under development in which the separation is based on different distributions of An and Ln between the salt and metallic Al phases. In this process molten aluminum alloy acts as both a reductant and a solvent into which the actinides are selectively extracted. It was demonstrated that a one-stage reductive extraction process, using a concentrated solution, allows a recovery of more than 99.3% of Pu and Am. In addition excellent separation factors between Pu and Ln well above 103 were obtained. In molten chloride media similar separations are developed by constant current electrorefining between a metallic alloy fuel (U60Pu20-Zr10Am2Nd3.5Y0.5Ce0.5Gd0.5) and an Al solid cathode. In a series of demonstration experiments, almost 25 g of metallic fuel was reprocessed and actinides collected as An-Al alloys on the cathode. Analysis of the An-Al deposits confirmed that an excellent An/Ln separation (An/Ln mass ratio = 2400) had been obtained. These results show that Al is a very promising material to be used in pyrochemical reprocessing of actinides.

Revue / Journal Title

Nuclear science and engineering    ISSN  0029-5639   CODEN NSENAO 

Source / Source

Congrès
Conference Atalante 2004, Nîmes , FRANCE (21/06/2004)
2006, vol. 153, no 3 (109 p.)  [Document : 9 p.] (25 ref.), pp. 253-261 [9 page(s) (article)]

Langue / Language

Anglais

Editeur / Publisher

American Nuclear Society, La Grange Park, IL, ETATS-UNIS  (1956) (Revue)

Mots-clés anglais / English Keywords

Pyrochemical reprocessing

;

Aluminium

;

Electrorefining

;

Irradiated nuclear fuel

;

Reprocessing

;

Plutonium

;

Extraction process

;

Separation process

;

Americium

;

Actinide

;

Thermodynamics

;

Lanthanide

;

Radioactive waste

;

Mots-clés français / French Keywords

Traitement pyrochimique

;

Aluminium

;

Raffinage électrolytique

;

Combustible irradié

;

Retraitement

;

Plutonium

;

Procédé extraction

;

Procédé séparation

;

Américium

;

Actinide

;

Thermodynamique

;

Lanthanide

;

Déchet radioactif

;

Mots-clés espagnols / Spanish Keywords

Aluminio

;

Refinación electrolítica

;

Combustible irradiado

;

Reprocesamiento

;

Plutonio

;

Procedimiento extracción

;

Proceso separación

;

Americio

;

Actínido

;

Termodinámica

;

Lantánido

;

Residuos radioactivos

;

Localisation / Location

INIST-CNRS, Cote INIST : 8020, 35400013898623.0060

Nº notice refdoc (ud4) : 18022762



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