Radionuclides containment in nuclear glasses: an overview

Author:

Gin Stephane1,Jollivet Patrick2,Tribet Magaly2,Peuget Sylvain2,Schuller Sophie2

Affiliation:

1. CEA Marcoule, DE2D SEVT , F-30207 Bagnols-sur-Ceze , France , Tel.: +33 466791465; Fax: +33 466796620

2. CEA Marcoule, DE2D SEVT , F-30207 Bagnols-sur-Ceze , France

Abstract

Abstract Radioactive waste vitrification has been carried out industrially in several countries for nearly 40 years. Research into the formulation and long term behavior of high and intermediate level waste glasses, mainly borosilicate compositions, is still continuing in order to (i) safely condition new types of wastes and (ii) design and demonstrate the safety of the disposal of these long-lived waste forms in a deep geological repository. This article presents a summary of current knowledge on the formulation, irradiation resistance and the chemical durability of these conditioning materials, with a special focus on the fate of radionuclides during glass processing and aging. It is shown that, apart from the situation for certain elements with very low incorporation rate in glass matrices, vitrification in borosilicate glass can enable waste loadings of up to ~20 wt% while maintaining the glass homogeneity for geological time scales and guaranteeing a high stability level in spite of irradiation and water contact.

Publisher

Walter de Gruyter GmbH

Subject

Physical and Theoretical Chemistry

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