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In Situ Radiation Damage Studies of Ca3Zr2FeAlSiO12 and Ca3Hf2FeAlSiO12

Published online by Cambridge University Press:  01 February 2011

Karl R Whittle ,
Mark Blackford ,
Gregory R Lumpkin ,
Katherine L Smith  and
Nestor J Zaluzec
Karl R Whittle
Affiliation:
mgb@ansto.gov.au, United States
Mark Blackford
Affiliation:
krw@ansto.gov.au, ANSTO, Institute of Materials Engineering, 2234, New South Wales, Australia
Gregory R Lumpkin
Affiliation:
greg.lumpkin@ansto.gov.au, ANSTO, Institute of Materials Engineering, Sydney, New South Wales, Australia
Katherine L Smith
Affiliation:
kath.smith@ansto.gov.au, ANSTO, Institute of Materials Engineering, Sydney, New South Wales, Australia
Nestor J Zaluzec
Affiliation:
zaluzec@aaem.amc.anl.gov, Argonne National Laboratory, Electron Microscopy Center, Chicago, Illinois, United States
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Abstract

Garnets, A3B2C3O12, are considered to be potential host phases for the immobilization of high-level nuclear waste as they can accommodate a number of elements of interest, including Zr, Ti and Fe. The naturally occurring garnet, kimzeyite, Ca3(Zr,Ti)2(Si,Al,Fe)3O12, can contain ˜30wt% Zr. An understanding of the radiation tolerance of these materials is crucial to their potential use in nuclear waste immobilization. In this study two synthetic analogues of kimzeyite of composition Ca3Zr2FeAlSiO12 and Ca3Hf2FeAlSiO12 were monitored in situ during irradiation with 1.0 MeV Kr ions using the intermediate voltage electron microscope-Tandem User Facility (IVEM) at Argonne National Laboratory. The structure of these materials was previously determined by neutron diffraction and 57Fe Mössbauer spectroscopy. Ca3Zr2FeAlSiO12 and Ca3Hf2FeAlSiO12 have very similar structural properties with cubic Ia3d symmetry, the only significant difference being the presence of Zr and Hf, respectively, on the 6 coordinated B sites.

Keywords

actinideradiation effectstransmission electron microscopy (TEM)
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1124: Symposium Q – Scientific Basis for Nuclear Waste Management XXXII , 2008 , 1124-Q10-08
Copyright
Copyright © Materials Research Society 2009

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