Ceramic conversion and densification of zirconium phosphonate sorbent materials

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dc.contributor.authorVeliscek-Carolan, Jen_AU
dc.contributor.authorThorogood, GJen_AU
dc.contributor.authorGregg, DJen_AU
dc.contributor.authorTansu, Men_AU
dc.contributor.authorHanley, TLen_AU
dc.date.accessioned2022-04-14T00:59:26Zen_AU
dc.date.available2022-04-14T00:59:26Zen_AU
dc.date.issued2018-04-01en_AU
dc.date.statistics2022-03-28en_AU
dc.description.abstractThe 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.en_AU
dc.identifier.citationVeliscek-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.2019.01.038en_AU
dc.identifier.issn0022-3115en_AU
dc.identifier.journaltitleJournal of Nuclear Materialsen_AU
dc.identifier.pagination327-334en_AU
dc.identifier.urihttps://doi.org/10.1016/j.jnucmat.2019.01.038en_AU
dc.identifier.urihttps://apo.ansto.gov.au/dspace/handle/10238/13001en_AU
dc.identifier.volume516en_AU
dc.language.isoenen_AU
dc.publisherElsevieren_AU
dc.subjectRadioactive wastesen_AU
dc.subjectZirconium compoundsen_AU
dc.subjectCeramicsen_AU
dc.subjectWaste formsen_AU
dc.subjectActinidesen_AU
dc.subjectSolidificationen_AU
dc.titleCeramic conversion and densification of zirconium phosphonate sorbent materialsen_AU
dc.typeJournal Articleen_AU
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