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Wasteforms for waste from advanced reprocessing

Published online by Cambridge University Press:  20 February 2017

Y-H Hsieh ,
D. Horlait ,
S. Humphry-Baker ,
E.R. Vance ,
D.J. Gregg ,
L. Edwards ,
T.D. Waite  and
W.E. Lee
Y-H Hsieh*
Affiliation:
Centre for Nuclear Engineering, Imperial College London, London, SW7 2AZ, United Kingdom
D. Horlait
Affiliation:
Centre for Nuclear Engineering, Imperial College London, London, SW7 2AZ, United Kingdom
S. Humphry-Baker
Affiliation:
Centre for Nuclear Engineering, Imperial College London, London, SW7 2AZ, United Kingdom
E.R. Vance
Affiliation:
Institute of Materials Engineering, Australian Nuclear Science and Technology Organization (ANSTO), Kirrawee, NSW 2232, Australia
D.J. Gregg
Affiliation:
Institute of Materials Engineering, Australian Nuclear Science and Technology Organization (ANSTO), Kirrawee, NSW 2232, Australia
L. Edwards
Affiliation:
Institute of Materials Engineering, Australian Nuclear Science and Technology Organization (ANSTO), Kirrawee, NSW 2232, Australia
T.D. Waite
Affiliation:
School of Civil and Environmental Engineering, The University of New South Wales, Sydney, NSW 2052, Australia
W.E. Lee
Affiliation:
Centre for Nuclear Engineering, Imperial College London, London, SW7 2AZ, United Kingdom
*
*(Email: y.hsieh14@imperial.ac.uk)
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Abstract

EURO-GANEX aims to recycle both major and minor actinides. As the final wastecomposition is free from actinides, adapted immobilization matrices should bedeveloped. Synroc is a potential wasteform that has proven itself to beefficient in immobilizing high-level wastes (HLW). In this study, a newcomposition of Synroc, Synroc-Z, is designed and characterized. The keymodification is in decreasing the amount of zirconolite phase, which is the mainhost phase for actinides and increasing the amount of other phases (hollanditeand perovskite). As designed the obtained amount of zirconolite is lower than inSynroc-C compositions. Synroc-Z samples were synthesized with a waste loading of20 wt.% at various temperatures and pressures via hot-pressing to determine theoptimum process parameters, which were determined to be 1150-1200°C and20 MPa, respectively.

Keywords

hot pressingwaste managementceramic

Information

Type
Articles
Information
MRS Advances , Volume 1 , Issue 63-64: Scientific Basis for Nuclear Waste Management XXXIX , 2016 , pp. 4255 - 4260
Copyright
Copyright © Materials Research Society 2017 

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References

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