Abstract

• A series of zirconolite ceramics of Ca1-xCexZrTi2-2xAl2xO7 were prepared. • All the solid solution ( x = 0–0.35) adopted zirconolite-2M (C2/c) structure. • XANES data revealed that Ce was partially reduced to the Ce3+ oxidation state. • The most favourable phase assemblage was found for composition with x = 0.20. A series of zirconolite ceramics with stoichiometry Ca 1-x Ce x ZrTi 2-2x Al 2x O 7 ( x = 0–0.35), considered as a host phase for the immobilisation of separated plutonium, were prepared from a mixture of oxide precursors by sintering in air at 1450 ° C. Ce was utilised as a structural surrogate for Pu, with Al added to provide charge compensation. XRD and electron diffraction analyses indicated crystallisation of the zirconolite-2M polytype for all compositions, accompanied by various secondary phases contingent on the doping level, consistent with microstructure observation. The relative yield of zirconolite phases remained above 94 wt.% for 0.05 < x < 0.20. It was determined that Ce was partially reduced to the Ce 3+ oxidation state and Al occupied mainly octahedral Ti sites. The incorporation rate of CeO 2 was calculated to be 9.27 wt.% in Ca 0.80 Ce 0.20 ZrTi 1.60 Al 0.40 O 7 with a comparatively high yield of 94.7 wt.%, which is representative of a PuO 2 incorporation rate of 14.86 wt.%.

Highlights

  • The United Kingdom currently holds the world’s largest inventory of separated plutonium, under civil safeguards, with an inventory of over 140 t forecast at the end of reprocessing options [1,2]

  • Begg et al attempted co-substitution of Pu/Np within zirconolite and deduced that whilst Pu could be accepted within solid solution, Pu valence was dependent on the processing atmosphere [12]

  • These results are indicative that the codoping of Ce and Al within the zirconolite structure was achieved within the range 0 < x ≤ 0.15

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Summary

Introduction

The United Kingdom currently holds the world’s largest inventory of separated plutonium, under civil safeguards, with an inventory of over 140 t forecast at the end of reprocessing options [1,2]. Current UK government policy is to reuse this separated plutonium as MOX fuel in light water reactors. An alternative option currently under consideration is immobilisation of plutonium within a chemically durable wasteform and disposal in an engineered geological disposal facility [3]. Titanate ceramics are a family of crystalline materials that are under development as hosts for. ✩ Dedication: In memorium, Dr Eric (Lou) Vance, 15 November 1942–7 March 2019, latterly Chief Scientist, Australian Nuclear Science and Technology Organization. High level radioactive waste streams due to superior aqueous durability with respect to vitrified wasteforms [4,5,6].

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