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Ceramic Immobilization Options for Technetium

Published online by Cambridge University Press:  20 March 2017

Martin C. Stennett ,
Tae-Hyuk Lee ,
Daniel J. Bailey ,
Erik V. Johnstone ,
Jong Heo  and
Neil C. Hyatt
Martin C. Stennett*
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Mappin Street, Sheffield, S1 3JD, UK.
Tae-Hyuk Lee
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Mappin Street, Sheffield, S1 3JD, UK. Department of Materials Science and Engineering and Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), Pohang, Gyeongbuk, 37673, Republic of Korea.
Daniel J. Bailey
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Mappin Street, Sheffield, S1 3JD, UK.
Erik V. Johnstone
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Mappin Street, Sheffield, S1 3JD, UK.
Jong Heo
Affiliation:
Department of Materials Science and Engineering and Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), Pohang, Gyeongbuk, 37673, Republic of Korea.
Neil C. Hyatt
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Mappin Street, Sheffield, S1 3JD, UK.
*
*(Email: m.c.stennett@sheffield.ac.uk)
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Abstract

Long half-life biologically active fission products, such as technetium-99, present particular problems for the disposal of spent nuclear fuel (SNF). Technetium is present in relatively high concentrations in fuel (approx. 1kg tonne-1 SNF) and has very high mobility in oxidizing environments. Technetium is therefore generally removed from SNF either by solvent extraction and reduction, during the PUREX process, or by sorption via ion exchange processes. Historically technetium has been disposed of via dilution and dispersion in the sea but stringent regulations now mean that the preferred long term option is immobilization in a highly stable and durable matrix. In this contribution we have looked at the synthesis of fluorite derivative crystalline host phases based on the zirconolite structure. Samples have been characterised by X-ray diffraction (XRD), scanning electron microscopy (SEM), energy dispersive spectroscopy (EDX), thermo-gravimetric analysis (TG), and mass spectroscopy (MS). We have used Mo as an inactive surrogate for Tc.

Keywords

ceramicwaste managementnuclear materials
Type
Articles
Information
MRS Advances , Volume 2 , Issue 13: Scientific Basis for Nuclear Waste Management XL , 2017 , pp. 753 - 758
Copyright
Copyright © Materials Research Society 2017 

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References

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