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Use of tri-laurylamine during the retreatment of irradiated fuels; Utilisation de la trilaurylamine au retraitement des combustibles irradies

Abstract

The purification of aqueous solutions of plutonium can be made by extraction of the Pu (IV) nitrate complex using trilaurylamine in dodecane. The principal physical properties of this solution are considered along with its extractive properties and the influence of foreign ions on the extraction. The application of this method of extraction in a processing cycle for irradiated material is proposed: either for a final purification process or for auxiliary cycles for recovering plutonium from metal production wastes, oxalate precipitation supernatants, or any general aqueous plutonium waste solution. Also proposed are clean-up procedures for regeneration of an extractive solution which has undergone chemical or radiolytic degradation. (authors) [French] La purification du plutonium contenu dans des solutions aqueuses peut etre effectuee par extraction du nitrate de l'ion tetravalent par la trilaurylamine diluee dans du dodecane. Les principales proprietes physiques de ce solvant sont passees en revue ainsi que ses proprietes extractives et l'influence des ions etrangers sur celles-ci. L'application de cette methode d'extraction dans le cycle de traitement des combustibles irradies est envisagee: soit dans le traitement de purification finale, soit dans les cycles annexes ayant trait a la recuperation de plutonium a partir des scories d'elaboration du metal, des eaux-meres  More>>
Authors:
Bathellier, A; Koehly, G; Perez, J J; Chesne, A [1] 
  1. Commissariat a l'Energie Atomique, Fontenay-aux-Roses (France). Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1964
Product Type:
Technical Report
Report Number:
CEA-R-2594
Resource Relation:
Other Information: 37 refs
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AQUEOUS SOLUTIONS; PLUTONIUM; PURIFICATION; REPROCESSING; SOLVENT EXTRACTION; SOLVENT PROPERTIES; SPENT FUELS; TRIDODECYLAMINE
OSTI ID:
20795952
Research Organizations:
CEA Fontenay-aux-Roses, 92 (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR06R2594097989
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
60 pages
Announcement Date:
Dec 22, 2006

Citation Formats

Bathellier, A, Koehly, G, Perez, J J, and Chesne, A. Use of tri-laurylamine during the retreatment of irradiated fuels; Utilisation de la trilaurylamine au retraitement des combustibles irradies. France: N. p., 1964. Web.
Bathellier, A, Koehly, G, Perez, J J, & Chesne, A. Use of tri-laurylamine during the retreatment of irradiated fuels; Utilisation de la trilaurylamine au retraitement des combustibles irradies. France.
Bathellier, A, Koehly, G, Perez, J J, and Chesne, A. 1964. "Use of tri-laurylamine during the retreatment of irradiated fuels; Utilisation de la trilaurylamine au retraitement des combustibles irradies." France.
@misc{etde_20795952,
title = {Use of tri-laurylamine during the retreatment of irradiated fuels; Utilisation de la trilaurylamine au retraitement des combustibles irradies}
author = {Bathellier, A, Koehly, G, Perez, J J, and Chesne, A}
abstractNote = {The purification of aqueous solutions of plutonium can be made by extraction of the Pu (IV) nitrate complex using trilaurylamine in dodecane. The principal physical properties of this solution are considered along with its extractive properties and the influence of foreign ions on the extraction. The application of this method of extraction in a processing cycle for irradiated material is proposed: either for a final purification process or for auxiliary cycles for recovering plutonium from metal production wastes, oxalate precipitation supernatants, or any general aqueous plutonium waste solution. Also proposed are clean-up procedures for regeneration of an extractive solution which has undergone chemical or radiolytic degradation. (authors) [French] La purification du plutonium contenu dans des solutions aqueuses peut etre effectuee par extraction du nitrate de l'ion tetravalent par la trilaurylamine diluee dans du dodecane. Les principales proprietes physiques de ce solvant sont passees en revue ainsi que ses proprietes extractives et l'influence des ions etrangers sur celles-ci. L'application de cette methode d'extraction dans le cycle de traitement des combustibles irradies est envisagee: soit dans le traitement de purification finale, soit dans les cycles annexes ayant trait a la recuperation de plutonium a partir des scories d'elaboration du metal, des eaux-meres oxaliques et d'une facon generale des solutions aqueuses contenant du plutonium. Des traitements de regeneration du solvant ayant subi des degradations chimique ou radiolytique, sont proposes. (auteurs)}
place = {France}
year = {1964}
month = {Jul}
}