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Ceramic Immobilisation Options for Technetium

Published online by Cambridge University Press:  29 November 2012

Martin C. Stennett ,
Daniel J. Backhouse ,
Colin L. Freeman  and
Neil C. Hyatt
Martin C. Stennett*
Affiliation:
Department of Materials Science and Engineering, The University of Sheffield, Sheffield, S13JD, United Kingdom.
Daniel J. Backhouse
Affiliation:
Department of Materials Science and Engineering, The University of Sheffield, Sheffield, S13JD, United Kingdom.
Colin L. Freeman
Affiliation:
Department of Materials Science and Engineering, The University of Sheffield, Sheffield, S13JD, United Kingdom.
Neil C. Hyatt
Affiliation:
Department of Materials Science and Engineering, The University of Sheffield, Sheffield, S13JD, United Kingdom.
*
*Email: [email protected]
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Abstract

Technetium-99 (99Tc) is a fission product produced during the burning of nuclear fuel and is particularly hazardous due to its long half life (210000 years), relatively high content in nuclear fuel (approx. 1 kg per ton of SNF), low sorption, and high mobility in aerobic environments. During spent nuclear fuel (SNF) reprocessing Tc is released either as a separate fraction or in complexes with actinides and zirconium. Although Tc has historically been discharged into the marine environment more stringent regulations mean that the preferred long term option is to immobilise Tc in a highly stable and durable matrix. This study investigated the feasibility of incorporating of Mo (as a Tc analogue) in a crystalline host matrix, synthesis by solid state synthesis under different atmospheres. Samples have been characterised with X-ray diffraction (XRD), scanning electron microscopy (SEM) and X-ray absorption spectroscopy (XAS).

Keywords

ceramicwaste managementnuclear materials
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1518: Symposium LL – Scientific Basis for Nuclear Waste Management XXXVI , 2012 , pp. 111 - 116
Copyright
Copyright © Materials Research Society 2012 

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References

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