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The Necessity for Scale Up in R&D: Approach for Waste Immobilisation in Cement by BNFL

Published online by Cambridge University Press:  15 February 2011

Graham A Fairhall  and
Eric W Miller
Graham A Fairhall
Affiliation:
Research and Development, British Nuclear Fuels plc, Sellafield, Seascale, Cumbria, CA20 1PG, UK.
Eric W Miller
Affiliation:
Research and Development, British Nuclear Fuels plc, Sellafield, Seascale, Cumbria, CA20 1PG, UK.
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Abstract

The full scale processing of nuclear wastes immobilised in cement utilises a wide range of chemical and physical parameters. The success of this work however, involves many factors and material properties which are affected by the actual scaling up processes. The paper outlines the approach and experience gained by BNFL to recognise and evaluate the major factors involved in order to successfully produce large scale stable products acceptable to the appropriate regulatory bodies and suitable for long term disposal.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 412: Symposium V – Scientific Basis for Nuclear Waste Management XIX , 1995 , 501
Copyright
Copyright © Materials Research Society 1996

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References

1. Fairhall, G A, The Encapsulation of Radioactive Wastes using Inorganic Cement, Proceedings of Environmental Remediation Conference ER '93, Augusta, USA, 1993.Google Scholar
2. Fairhall, G A, The Treatment and Encapsulation of Intermediate Level Wastes at Sellafield, Proceedings of RECOD '94 Conference, London, 1994.Google Scholar
3. Fairhall, G A, Francis, A J and Matthews, G, The Product Evaluation Development Programme in Support of Treatment Processes for ILW Arising from Reprocessing Operations at BNFL, Proceedings of the International Seminar on Radioactive Waste Products, KFA Julich, West Germany, pp. 37–43, 1985.Google Scholar
4. Fairhall, G A, Objectives and Scope of BNFL/DOE Product Evaluation Development Programme, DOE-RW-89.050, 1989.Google Scholar
5. Fairhall, G A, Effect of Process Operational Variables on the Product Properties of Encapsulated Intermediate Level Wastes, Proceedings of International Conference - Radioactive Waste Management 2, BNES, Brighton, pp. 79–84, 1989.Google Scholar
6. Fairhall, G A and Palmer, J, The Encapsulation of Magnox Swarf in Cement in the United Kingdom, Cement and Concrete Research, Vol.22, pp. 293–298, 1992.Google Scholar
7. Palmer, J and Fairhall, G A, Properties of Cement Systems Containing Intermediate Level Wastes, Cement and Concrete Research, Vol.22, pp. 325–330, 1992.Google Scholar