膨润土
吸附
流出物
化学
环境化学
化学工程
制浆造纸工业
核化学
环境科学
环境工程
有机化学
工程类
作者
Yi‐Hui Lin,Yuhan Li,Yating Yang,Po-Hsiang Chang
摘要
This study investigated strontium (Sr2+) adsorption by Taiwan Zhi-Shin bentonite (cation exchange capacity (CEC): 80-86 meq 100 g-1) using Sr(NO3)2-simulated nuclear waste. Kinetic analysis revealed pseudo-second-order adsorption kinetics, achieving 95% Sr2+ removal within 5 min at pH 9. Isothermal studies showed a maximum capacity of 0.28 mmol g-1 (56 meq 100 g-1) at 15 mmol L-1 Sr2+, accounting for 65-70% CEC and fitting the Freundlich model. Cation exchange was the dominant mechanism (84% contribution), driven by Sr2+ displacing interlayer Ca2+. Alkaline conditions (pH > 9) enhanced adsorption through improved surface charge and electrostatic attraction. Thermodynamic studies demonstrated temperature-dependent behavior: increasing temperature reduced adsorption at 0.01 mM Sr2+ but increased efficiency at 10 mM. Na+ addition suppressed adsorption, aligning with cation exchange mechanisms. Molecular dynamics simulations identified hydrated Ca2+-Sr2+ water bridges interacting with bentonite via hydrogen-bonding networks. The material exhibits rapid kinetics (5 min equilibrium), alkaline pH optimization, and resistance to ion interference, making it suitable for emergency Sr2+ treatment. It shows promise as a cost-effective and good performing adsorbent for radioactive waste solutions.
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