This paper gives an historical review of work carried out in India on the development of vitreous matrices for the incorporation of high level radioactive Purex waste. The work was conducted in such a way as to enable a wide choice of glass compositions: the glass forming areas identified are given in the form of tri-axial diagrams where the waste oxide occupies one apex. The melting behaviour, long term retention of fission products and the factors influencing the retention of fission products, together with the physical and chemical properties of selected glasses are presented.
Origin
Cgcri, India
Journal Title
Glass Technology 45 3 June 2004 117-125
Sector
General
Class
G 2830