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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: [email protected])
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Abstract

EURO-GANEX aims to recycle both major and minor actinides. As the final waste composition is free from actinides, adapted immobilization matrices should be developed. Synroc is a potential wasteform that has proven itself to be efficient in immobilizing high-level wastes (HLW). In this study, a new composition of Synroc, Synroc-Z, is designed and characterized. The key modification is in decreasing the amount of zirconolite phase, which is the main host phase for actinides and increasing the amount of other phases (hollandite and perovskite). As designed the obtained amount of zirconolite is lower than in Synroc-C compositions. Synroc-Z samples were synthesized with a waste loading of 20 wt.% at various temperatures and pressures via hot-pressing to determine the optimum process parameters, which were determined to be 1150-1200°C and 20 MPa, respectively.

Keywords

hot pressingwaste managementceramic
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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