Community Research and Development Information Service - CORDIS

Abstract

High level nuclear waste from reprocessing of spent nuclear fuel has to be solidified in a stable matrix for safe long-term storage. Vitrification in borosilicate glasses is the technique accepted worldwide as the best combination of engineering constraints from fabrication and physicochemical properties of the matrix. A number of different glasses were developed in different national programmes. The criteria and reasons for selecting the final compositions are briefly described. Emphasis is placed on the French product R7T7 and on thermal and physicochemical properties, though glasses developed in other national projects are also considered. Knowledge accumulated in the past is used to evaluate and predict the long-term evolution of the glass under storage conditions.

Additional information

Authors: MATZKE H J, JRC Karlsruhe (DE);VERNAZ E, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: 8th International Symposium on Thermodynamics of Nuclear Materials, Snowbird (US), August 16-21, 1992
Availability: Available from (1) as Paper EN 37235 ORA
Record Number: 199211469 / Last updated on: 1994-11-29
Category: PUBLICATION
Original language: en
Available languages: en