• Title/Summary/Keyword: Surface complexation modelling

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Influence of Ca-Na-Cl physicochemical solution properties on the adsorption of Se(-II) onto granite and MX-80 bentonite

  • Joshua Racette ;Andrew Walker ;Shinya Nagasaki ;Tianxiao Tammy Yang ;Takumi Saito ;Peter Vilks
    • Nuclear Engineering and Technology
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    • v.55 no.10
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    • pp.3831-3843
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    • 2023
  • The adsorption behaviour of Se(-II) onto granite and MX-80 bentonite in Ca-Na-Cl solutions has been studied utilizing adsorption experiments and surface complexation modelling. Adsorption kinetic experiments allude to steady-state adsorption periods after 7 days for granite and 14 days for MX-80 bentonite. Batch adsorption experiments were carried out to determine the influence that the physicochemical solution properties would have on Se(-II) adsorption behaviour. Adsorption of Se(-II) onto granite and MX-80 bentonite follows the trend of anionic adsorption, with a decrease in Rd values as the solution pH increased. There is also an ionic strength influence on the adsorption of Se(-II) onto granite with a decrease in the Rd value as the ionic strength increased. This effect is not found when observing Se(-II) adsorption onto MX-80 bentonite. Final experiments with a representative groundwater, determined that the adsorption of Se(-II) onto granite and MX-80 bentonite returned Rd values of (1.80 ± 0.10) m3·kg-1 and (0.47 ± 0.38) m3·kg-1, respectively. In support of the experiments, a surface complexation modelling approach has been employed to simulate the adsorption of Se(-II) onto granite and MX-80 bentonite, where it was determined that two different surface complexes, ≡S_Se- and ≡SOH2+_H2 were capable of simulating Se(-II) adsorption behaviour.

Molybdenum release from high burnup spent nuclear fuel at alkaline and hyperalkaline pH

  • Sonia Garcia-Gomez;Javier Gimenez;Ignasi Casas;Jordi Llorca;Joan De Pablo;Albert Martinez-Torrents;Frederic Clarens;Jakub Kokinda;Luis Iglesias;Daniel Serrano-Purroy
    • Nuclear Engineering and Technology
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    • v.56 no.1
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    • pp.34-41
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    • 2024
  • This work presents experimental data and modelling of the release of Mo from high-burnup spent nuclear fuel (63 MWd/kgU) at two different pH values, 8.4 and 13.2 in air. The release of Mo from SF to the solution is around two orders of magnitude higher at pH = 13.2 than at pH = 8.4. The high Mo release at high pH would indicate that Mo would not be congruently released with uranium and would have an important contribution to the Instant Release Fraction, with a value of 5.3%. Parallel experiments with pure non irradiated Mo(s) and XPS determinations indicated that the faster dissolution at pH = 13.2 could be the consequence of the higher releases from metallic Mo in the fuel through a surface complexation mechanism promoted by the OH- and the oxidation of the metal to Mo(VI) via the formation of intermediate Mo(IV) and Mo(V) species.