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Simulation of Self-Irradiation of High-Sodium Content Nuclear Waste Glasses

Published online by Cambridge University Press:  19 October 2011

Michael I. Ojovan ,
Olga G. Batyukhnova ,
Michael I. Ojovan  and
William E. Lee
Michael I. Ojovan
Affiliation:
[email protected], University of Sheffield, Immobilisation Science Laboratory, Department of Engineering Materials, Sir Robert Hadfield Building, Mappin Street, Sheffield, S1 3JD, United Kingdom, 0044-114-2226033, 0044-114-2225943
Olga G. Batyukhnova
Affiliation:
[email protected], SUE SIA “Radon”, International Education Training Centre, The 7-th Rostovsky Lane 2/14, Moscow, 119121, Russian Federation
Michael I. Ojovan
Affiliation:
[email protected], University of Sheffield, Immobilisation Science Laboratory, Department of Engineering Materials, Sir Robert Hadfield Building, Mappin Street, Sheffield, S1 3JD, United Kingdom
William E. Lee
Affiliation:
[email protected], Imperial College London, Department of Materials, South Kensington Campus,Exhibition Road, London, SW7 2AZ, United Kingdom
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Abstract

Alkali-borosilicate glasses are widely used in nuclear industry as a matrix for immobilisation of hazardous radioactive wastes. Durability or corrosion resistance of these glasses is one of key parameters in waste storage and disposal safety. It is influenced by many factors such as composition of glass and surrounding media, temperature, time and so on. As these glasses contain radioactive elements most of their properties including corrosion resistance are also impacted by self-irradiation.

The effect of external gamma-irradiation on the short-term (up to 27 days) dissolution of waste borosilicate glasses at moderate temperatures (30¢X to 60¢XC) was studied. The glasses studied were Magnox Waste glass used for immobilisation of HLW in UK, and K-26 glass used in Russia for ILW immobilisation. Glass samples were irradiated under ×-source (Co-60) up to doses 1 and 11 MGy. Normalised rates of elemental release and activation energy of release were measured for Na, Li, Ca, Mg, B, Si and Mo before and after irradiation. Irradiation up to 1 MGy results in increase of leaching rate of almost all elements from both MW and K-26 with the exception of Na release from MW glass. Further irradiation up to a dose of 11 MGy leads to the decrease of elemental release rates to nearly initial value. Another effect of irradiation is increase of activation energies of elemental release.

Keywords

radiation effectswaste managementcorrosion
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 985: Symposium NN – Scientific Basis for Nuclear Waste Management XXX , 2006 , 0985-NN11-01
Copyright
Copyright © Materials Research Society 2007

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