Treatment of Radioactive Liquid Waste Using Bentonite

  • Aamir Abdullah Mohammed Physics Department, College of Science, University of Baghdad
  • Hayder S. Hussain Physics Department, College of Science, University of Baghdad
  • Salam K. Al-Nasri Ministry of Science and Technology
Keywords: Cesium-137, Bentonite, Isotherm

Abstract

Radioactive liquid waste contaminated with cesium-137 found in the radiochemistry laboratories at Tuwaitha site, south of Baghdad, was treated in this work. Bentonite was used as a sorbent material for the removal of radioactive cesium-137 from liquid waste by ion exchange method. The results indicated that the best removal efficiency obtained was 95.13% with experimental conditions of 2 h mixture time, 0.04 g sorbent mass, and pH=10 for the radioactive liquid. It was found that the experimental results match well with Langmuir and Freundlich models, with better matching with the latter.

Published
2021-03-30
How to Cite
Aamir Abdullah Mohammed, Hayder S. Hussain, & Salam K. Al-Nasri. (2021). Treatment of Radioactive Liquid Waste Using Bentonite. Iraqi Journal of Science, 62(3), 871-877. https://doi.org/10.24996/ijs.2021.62.3.18
Section
Physics