Novel Portland cement matrices incorporating a γ-MnO2/Ag2O hydrogen/tritium getter -structure changes and trapping performance

Lanier, S.; Davy, Catherine; Albert-Mercier, Cyrille; Farcy, Oriane; Coumes, C. Cau Dit; Lambertin, David

doi:10.1016/j.jnucmat.2022.153819

Cited by 3 publications

(1 citation statement)

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“…When the ion exchange sites of resins are saturated with radionuclides, they lose purification capacity and are discharged from treatment columns, thus forming spent radioactive resins to be solidified and disposed of. Cement solidification, with the advantages of low cost, operability, and good radiation resistance of the solidified wasteforms, is currently the most widely used solidification technique for treating spent resin before final disposal [7][8][9][10][11][12][13][14][15]. New cement compositions besides ordinary Portland cement (OPC) offers fresh perspectives on radioactive waste solidification, especially for wastes that are challenging for OPC to solidify [16,17].…”

Section: Introductionmentioning

confidence: 99%

Metakaolin-Reinforced Sulfoaluminate-Cement-Solidified Wasteforms of Spent Radioactive Resins—Optimization by a Mixture Design

Wang

Liu

et al. 2022

Coatings

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Cement solidification is a main technique for radioactive waste treatment to reduce its risk to the environment and human health. However, this method underperforms when dealing with spent radioactive ion-exchange resin, taking much space, and costing much money for final disposal. In this work, simulated spent radioactive resin was solidified using a metakaolin-reinforced sulfoaluminate cement system, which was optimized by a mixture design based on the effects of components and parameters, and the durability of solidified wasteforms was assessed in terms of strength and Cs(I) leaching. Solidified by an optimized formula of 40 wt.% spent resin, 55.8 wt.% sulfoaluminate cement, 2.2 wt.% metakaolin, and 2 wt.% water reducer, the resin loading in wasteforms reached 64% and the compressive strength 13.7 MPa. The dominant mineral phases of hydration products were ettringite crystalline of acicular and columnar morphology, with small amounts of scattered amorphous clusters of aluminum gels and C–S–H gels. Metakaolin, a source of aluminum, promoted the growth of ettringite, which facilitated (1) the encapsulation of resin beads with high strengths, even in acidic environments or during frequent freezing-thawing, and (2) the retention of Cs(I), with a 42 day leaching rate of 2.3 × 10−4 cm/day. This work offers a technical justification for spent resin solidification in the metakaolin-reinforced sulfoaluminate cement system, which is an applicational solution for the efficient treatment of radioactive waste.

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