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Neodymium Incorporation in Zirconolite-Based Glass-Ceramics

Published online by Cambridge University Press:  21 March 2011

P. Loiseau ,
D. Caurant ,
N. Baffier  and
C. Fillet
P. Loiseau
Affiliation:
Laboratoire de Chimie Appliquée de l'Etat Solide (UMR CNRS 7574), ENSCP, 11 rue Pierre et Marie Curie, 75231 Paris Cedex 05, France
D. Caurant
Affiliation:
Laboratoire de Chimie Appliquée de l'Etat Solide (UMR CNRS 7574), ENSCP, 11 rue Pierre et Marie Curie, 75231 Paris Cedex 05, France
N. Baffier
Affiliation:
Laboratoire de Chimie Appliquée de l'Etat Solide (UMR CNRS 7574), ENSCP, 11 rue Pierre et Marie Curie, 75231 Paris Cedex 05, France
C. Fillet
Affiliation:
Commissariat á l'Energie Atomique (CEA), Centre d'Etudes de la Vallée du Rhône, DCC/DRRV/SCD/LEBM, BP 171, 30207 Bagnols sur Cèze, France
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Abstract

The investigations on enhanced reprocessing of nuclear spent fuel, and notably on separating the long-lived minor actinides, such as Am and Cm, from the other fission products have led to the development of highly durable specific matrices such as glass-ceramics for their immobilization. This study deals with the characterization of zirconolite (CaZrTi2O7) based glass-ceramics synthesized by devitrification of an aluminosilicate parent glass. Trivalent actinide ions were simulated by neodymium, which is a paramagnetic local probe. Glass-ceramics with Nd2O3 contents ranging from 0 to 10 weight % were prepared by heat treatment of a parent glass at two different growth temperatures: 1050° and 1200°C. X-ray diffraction (XRD), energy dispersive X-ray analysis (EDX) and electron spin resonance (ESR) measurements clearly indicate that Nd3+ ions are partly incorporated in zirconolite crystals formed in the bulk of the glass-ceramic samples. The amount of neodymium in the crystalline phase was estimated using ESR results and was found to decrease with increasing either heat treatment temperature or total Nd2O3 content.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 169
Copyright
Copyright © Materials Research Society 2001

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