Effects of elevated temperature on Wyoming bentonite and its implications for sorption of radioactive strontium

Bentonite is a key barrier material in deep geological facilities for spent nuclear fuel, where it may be exposed to temperatures >100 °C because of radiogenic heating. Understanding how prolonged heating affects its physicochemical properties and radionuclide retention capacity is critical for ensuring long-term repository safety. This study investigated the impacts of dry heating (unconfined, evaporation allowed) at 150 °C for 36 months on the mineralogical and geochemical stability of a Wyoming bentonite, chosen for the Finnish geological disposal facility, and its subsequent sorption behavior with 90 Sr. Although the bentonite mineralogy remained mostly stable, combined X-ray diffraction, cation exchange capacity, titrations, demonstrated partial Na to Ca exchange within montmorillonite's interlayer following heating, and specific surface area analyses revealed a > 50 % reduction in specific surface area (30 to 14 m 2 /g). Colloid stability tests revealed that bentonite colloids did not form under repository-relevant saline conditions ( I = 0.2 M), and heat treatment did not significantly impact colloid formation in reduced ionic-strength systems. Sorption isotherms demonstrated that Sr sorption was strongly pH-dependent, increasing from ∼40 % at pH 8 to ∼90 % at pH 13, and heating slightly enhanced Sr retention at pH 8. Two-site protolysis non-electrostatic surface complexation and cation exchange modelling suggested that in unheated bentonite, Sr was bound via a combination of surface complexation (∼30 %) and cation exchange (∼70 %) at pH 8, while at pH 13, sorption shifted towards surface complexation. However, after heating, cation exchange dominated at both pH values. Extended X-ray absorption fine structure analysis confirmed outer-sphere Sr sorption at pH 8 and increasing inner-sphere complexation at pH 13. Together, these findings highlight that despite minor physicochemical alterations, bentonite retained its Sr sorption potential, supporting its continued suitability as a buffer material in the ONKALO® repository. • Physicochemical changes in Wyoming bentonite were studied after 36 months of heating at 150 °C. • Bentonite was largely stable; interlayer Ca replaced Na and surface area decreased by over 50 %. • Sr sorption at pH 8 and 13 was largely unaffected after following heating. • Sr retention mechanisms were investigated using modelling and X-ray absorption spectroscopy.

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Publication Details

Journal
Applied Clay Science
Published
2025-05-15
DOI
https://doi.org/10.1016/j.clay.2025.107865
Citations
4
Primary Topic
Radioactive element chemistry and processing
Type
article
Field-Weighted Citation Impact
2.15

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article

Effects of elevated temperature on Wyoming bentonite and its implications for sorption of radioactive strontium

Markus Olin, Damien Prieur, Kathleen A. Law, Marja Siitari‐Kauppi et al.
4 citations
Applied Clay Science
Radioactive element chemistry and processing
2.15
article

Effects of elevated temperature on Wyoming bentonite and its implications for sorption of radioactive strontium

Markus Olin, Damien Prieur, Kathleen A. Law, Marja Siitari‐Kauppi, René Bès, Noora Pakkanen, Gianni F. Vettese, Mika Niskanen, Nina Huittinen, Taavi Vierinen, Xiaodong Li, Afrida Fairuz, Lilia Sirén
article en
4 citations

Abstract

Bentonite is a key barrier material in deep geological facilities for spent nuclear fuel, where it may be exposed to temperatures >100 °C because of radiogenic heating. Understanding how prolonged heating affects its physicochemical properties and radionuclide retention capacity is critical for ensuring long-term repository safety. This study investigated the impacts of dry heating (unconfined, evaporation allowed) at 150 °C for 36 months on the mineralogical and geochemical stability of a Wyoming bentonite, chosen for the Finnish geological disposal facility, and its subsequent sorption behavior with 90 Sr. Although the bentonite mineralogy remained mostly stable, combined X-ray diffraction, cation exchange capacity, titrations, demonstrated partial Na to Ca exchange within montmorillonite's interlayer following heating, and specific surface area analyses revealed a > 50 % reduction in specific surface area (30 to 14 m 2 /g). Colloid stability tests revealed that bentonite colloids did not form under repository-relevant saline conditions ( I = 0.2 M), and heat treatment did not significantly impact colloid formation in reduced ionic-strength systems. Sorption isotherms demonstrated that Sr sorption was strongly pH-dependent, increasing from ∼40 % at pH 8 to ∼90 % at pH 13, and heating slightly enhanced Sr retention at pH 8. Two-site protolysis non-electrostatic surface complexation and cation exchange modelling suggested that in unheated bentonite, Sr was bound via a combination of surface complexation (∼30 %) and cation exchange (∼70 %) at pH 8, while at pH 13, sorption shifted towards surface complexation. However, after heating, cation exchange dominated at both pH values. Extended X-ray absorption fine structure analysis confirmed outer-sphere Sr sorption at pH 8 and increasing inner-sphere complexation at pH 13. Together, these findings highlight that despite minor physicochemical alterations, bentonite retained its Sr sorption potential, supporting its continued suitability as a buffer material in the ONKALO® repository. • Physicochemical changes in Wyoming bentonite were studied after 36 months of heating at 150 °C. • Bentonite was largely stable; interlayer Ca replaced Na and surface area decreased by over 50 %. • Sr sorption at pH 8 and 13 was largely unaffected after following heating. • Sr retention mechanisms were investigated using modelling and X-ray absorption spectroscopy.

Applied Clay ScienceVol. 274
University of Helsinki (FI), Helsinki Institute of Physics (FI), Helmholtz-Zentrum Dresden-Rossendorf (DE), European Synchrotron Radiation Facility (FR), Posiva (Finland) (FI), Freie Universität Berlin (DE), VTT Technical Research Centre of Finland (FI)
HORIZON EUROPE Framework Programme, Horizon 2020
Openalex Percentile: Top 13%
Radioactive element chemistry and processing
2.15
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