Please use this identifier to cite or link to this item: https://apo.ansto.gov.au/dspace/handle/10238/13001
Title: Ceramic conversion and densification of zirconium phosphonate sorbent materials
Authors: Veliscek-Carolan, J
Thorogood, GJ
Gregg, DJ
Tansu, M
Hanley, TL
Keywords: Radioactive wastes
Zirconium compounds
Ceramics
Waste forms
Actinides
Solidification
Issue Date: 1-Apr-2018
Publisher: Elsevier
Citation: Veliscek-Carolan, J., Thorogood, G. J., Gregg, D. J., Tansu, M., & Hanley, T. L. (2019). Ceramic conversion and densification of zirconium phosphonate sorbent materials. Journal of Nuclear Materials, 516, 327-334. doi:10.1016/j.jnucmat.2019.01.038
Abstract: The simple conversion of zirconium phosphonate sorbent materials, with known affinity for lanthanide elements, to durable ceramic waste forms via thermal treatment has been demonstrated. The use of zirconium phosphonate enables both removal of targeted elements from spent nuclear fuel and immobilisation into leach resistant solid products to be achieved using a single material. Thermal conversion was performed on the zirconium phosphonate both before and after loading with europium, which acted as a surrogate for the chemically similar minor actinides. Without europium loaded, the zirconium phosphonate sorbent formed predominantly KZr2(PO4)3 upon heating, independent of the processing conditions used. A maximum relative density of 87% was achieved with cold isostatic pressing (200 MPa) and sintering at 1200 °C for 12 h. When the zirconium phosphonate sorbent was loaded with europium, the phase composition formed upon thermal treatment was more complex. Specifically, mixtures of ZrP2O7, Eu0.33Zr2(PO4)3, EuPO4 and Zr2O(PO4)2 were formed, with phase compositions depending on the temperatures and pressures used. The simplest phase composition for the europium loaded material was achieved via uniaxial pressing (120 MPa) and sintering at 1300 °C for 1 h, although the ceramic pellet produced under these conditions had a relative density of only 53%. The loaded europium deported primarily to a EuPO4 phase, which is known to be highly stable and leach resistant. As such, these zirconium phosphonate materials have potential utility for treatment of nuclear wastes. © 2019 Elsevier B.V.
URI: https://doi.org/10.1016/j.jnucmat.2019.01.038
https://apo.ansto.gov.au/dspace/handle/10238/13001
ISSN: 0022-3115
Appears in Collections:Journal Articles

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