Abstract

The behaviour of U(VI) in hyperalkaline fluid/calcite systems was studied over a range of U(VI) concentrations (5.27×10−5μM to 42.0μM) and in two high pH systems, young and old synthetic cement leachate in batch sorption experiments. These systems were selected to be representative of young- (pH 13.3) and old-stage (pH 10.5) leachate evolution within a cementitious geological disposal facility. Batch sorption experiments, modelling, extended X-ray absorption fine structure spectroscopy, electron microscopy, small angle X-ray scattering and luminescence spectroscopy were used to define the speciation of U(VI) across the systems of study. At the lowest concentrations (5.27×10−5μM 232U(VI)) significant U removal was observed for both old and young cement leachates, and this was successfully modelled using a first order kinetic adsorption modelling approach. At higher concentrations (>4.20μM) in the young cement leachate, U(VI) showed no interaction with the calcite surface over an 18month period. Small angle X-ray scattering techniques indicated that at high U concentrations (42.0μM) and after 18months, the U(VI) was present in a colloidal form which had little interaction with the calcite surface and consisted of both primary and aggregated particles with a radius of 7.6±1.1 and 217±24Å, respectively. In the old cement leachate, luminescence spectroscopy identified two surface binding sites for U(VI) on calcite: in the system with 0.21μM U(VI), a liebigite-like Ca2UO2(CO3)3 surface complex was identified; at higher U(VI) concentrations (0.42μM), a second binding site of undetermined coordination was identified. At elevated U(VI) concentrations (>2.10μM) in old cement leachate, both geochemical data and luminescence spectroscopy suggested that surface mediated precipitation was controlling U(VI) behaviour. A focused ion beam mill was used to create a section across the U(VI) precipitate–calcite interface. Transmission electron microscope images of the section revealed that the calcite surface was coated with a nano crystalline, U containing phase. Selected area electron diffraction images of the U precipitate which was formed at a U(VI) concentration of 4.20μM were consistent with the formation of calcium uranate. XAS spectroscopy at higher concentrations (⩾21.0μM) suggested the formation of a second U(VI) phase, possibly a uranyl oxyhydroxide phase.These results indicated that in the young cement leachate, U(VI) did not react with the calcite surface unless U(VI) concentrations were very low (5.27×10−5μM). At higher concentrations, speciation calculations suggested that U(VI) was significantly oversaturated and experimental observations confirmed it existed in a colloidal form that interacted with the mineral surface only weakly. In the old cement leachate systems at low concentrations batch sorption and luminescence data suggested that U(VI) removal was being driven by a surface complexation mechanism. However, at higher concentrations, spectroscopic methods suggest a combination of both surface complexation and surface mediated precipitation was responsible for the observed removal. Overall, U(VI) behaviour in hyperalkaline calcite systems is distinct from that at circumneutral pH conditions: at high pH and anything but low U(VI) concentrations, a surface mediated precipitation mechanism occurs; this is in contrast to circumneutral pH conditions where U(VI) surface complexation reactions tend to dominate.

Highlights

  • In many countries the long-term management of intermediate level radioactive wastes will be for their final disposal in a deep Geological Disposal Facility (GDF) (NEA, 2004; DEFRA, 2008; Schwyn et al, 2012)

  • Selected Area Electron Diffraction (SAED) data from this study suggested the formation of calcium uranate in the calcite systems at a U(VI) concentration of 4.20 lM

  • The data collected in this study demonstrate the complex behaviour of U(VI), with the mechanisms of interaction changing from surface complexation, to surface precipitation, to formation of a U(VI) colloidal phase depending on the cement leachate pH, amount of calcite, and U(VI) concentration (Table 6)

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Summary

Introduction

In many countries the long-term management of intermediate level radioactive wastes will be for their final disposal in a deep Geological Disposal Facility (GDF) (NEA, 2004; DEFRA, 2008; Schwyn et al, 2012). “shotcrete”) will be utilised in many designs This means that consideration of the alkaline conditions that result from cement materials is of wide relevance (Schmidt, 1991; Schwyn et al, 2012). In a cementitious GDF over time, the portlandite (Ca(OH)2) and calcium silicate hydrate (C–S–H) components of the cement will undergo carbonation via reaction with carbonate in groundwaters to form minerals including calcite (CaCO3; Dow and Glasser, 2003). This will increase the quantity of calcite present in any evolved cementitious GDF. Calcite clearly has the potential to be an important reactive mineral phase for radionuclides within the GDF environment

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