Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 24(1); 2026
  • Article

Research Paper

Journal of Nuclear Fuel Cycle and Waste Technology 2026;24(1):. Published online: Mar, 30, 2026

Sorption Thermodynamics of Cs(I) and Sr(II) Onto Na-exchanged Bentonil-WRK Montmorillonite

  • Seonggyu Choi1,*, Hyewon Ji2, Song-I Yu2, Hyun-Kyu Lee1, and Sang-Ho Lee1

    1Korea Atomic Energy Research Institute, 111, Daedeok-daero 989beon-gil, Yuseong-gu, Daejeon 34057, Republic of Korea
    2Chungnam National University, 99, Daehak-ro, Yuseong-gu, Daejeon 34134, Republic of Korea
Abstract

Understanding how saline water intrusion alters the performance of bentonite buffer is critical for the reliable safety assessment of a high-level radioactive waste repository. This study investigated sorption thermodynamics of Cs(I) and Sr(II) onto Na-exchanged Bentonil-WRK montmorillonite. Batch sorption experiments were conducted under ambient conditions (T = 25℃, pH 4–10, S/L = 5 g·L−1, I = 0.01 mol·L−1 NaCl), followed by inverse modeling of the resulting data. The sorption of Cs(I) was dominated by cation exchange (XNa + Cs+ ⇌ XCs + Na+, log K = 1.48 ± 0.02) with a minor contribution from edge surface complexation at silanol site (≡SiOH + Cs+ ⇌ ≡SiOCs + H+, log K = −5.36 ± 0.70). In contrast, Sr(II) uptake involved a more complex mechanism comprising cation exchange (2XNa + Sr2+ ⇌ X2Sr + 2Na+, log K = 0.47 ± 0.06), interlayer ion-pairing with chloride (XNa + Sr2+ + Cl− ⇌ XSrCl + Na+, log K = 3.05 ± 0.33), and edge complexation (≡SiOH + Sr2+ ⇌ ≡SiOSr+ + H+, log K = −6.04 ± 0.94). The derived thermodynamic parameters complement the radionuclide sorption database for Ca-type bentonite, reducing uncertainty by enabling process-based evaluation of clay buffer performance under long-term geochemical evolution scenarios.

Keywords

Sorption, Montmorillonite, Cesium, Strontium, Ion exchange, Surface complexation