Treatment of Radioactive Liquid Waste Using Bentonite

Authors

  • 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

DOI:

https://doi.org/10.24996/ijs.2021.62.3.18

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.

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Published

2021-03-30

Issue

Section

Physics

How to Cite

Treatment of Radioactive Liquid Waste Using Bentonite. (2021). Iraqi Journal of Science, 62(3), 871-877. https://doi.org/10.24996/ijs.2021.62.3.18

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