Community Research and Development Information Service - CORDIS

Abstract

The report describes research by several laboratories on the behaviour, in aqueous and salt environments, of borosilicate glass and glass ceramics proposed for the solidification of nuclear wastes by the European Community. Results were obtained on inactive simulates, doped materials, and on borosilicate glass containing real radioactive waste. The influence of any important parameters were studied: leaching mode, nature of the leachant, pH, pressure, temperature, duration of the treatment, etc. The results of tests lasting or as little as a few hours or for as long as several hundred days, at temperatures up to 200 degrees C or under pressures up to 200 bars, are presented. Numerous analytical techniques (ESCA, EMP, IRR, SEM, etc.) were used to determine the structure and the chemical composition of the altered layer developed by hydration at the glass surface. Information is also given on physical properties of the borosilicate glass: crystallization phase separation, alpha irradiation stability, mechanical and thermal stability, etc. Finally, preliminary results on the structure and composition of hollandite ceramics are given.

Additional information

Authors: ENGELMANN CH CENTRE D'ETUDES NUCLEAIRES DE SACLAY (FRANCE), CENTRE D'ETUDES NUCLEAIRES DE SACLAY (FRANCE)
Bibliographic Reference: EUR 9268 EN (1984) FS, 223 P., BFR 700, EUROFFICE, LUXEMBOURG POB 1003
Availability: Can be ordered online
Record Number: 1989123021500 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en