Removal of U(VI) from simulated liquid waste using synthetic organic resin
- Authors: Massoud A.1, Waly S.A.2, Abou El-Nour F.3
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Affiliations:
- Cyclotron Facility, Nuclear Research Center
- Accelerators Department
- Nuclear Chemistry Department
- Issue: Vol 59, No 3 (2017)
- Pages: 272-279
- Section: Article
- URL: https://ogarev-online.ru/1066-3622/article/view/223921
- DOI: https://doi.org/10.1134/S1066362217030092
- ID: 223921
Cite item
Abstract
Poly(acrylic acid–dimethylaminoethyl methacrylate) was prepared by γ-radiation-induced copolymerization at a radiation dose of 60 kGy and a dose rate of 1.25 kGy h–1. The resin obtained was used to remove U(VI) from simulated solution of the waste from the Fuel Manufacturing Pilot Plant (FMPP). A preliminary test of U(VI) adsorption onto the resin showed high affinity of this resin for U(VI) ions. The adsorption behavior toward the U(VI) ions was studied in relation to the contact time, pH, temperature, resin dosage, and initial concentration of metal ions. The adsorption isotherms of uranium onto the resin were described using the Langmuir and Freundlich models, with the Langmuir model being more adequate to the experimental equilibrium data. Without foreign ions, the maximum adsorption capacity of the resin for U(VI) was 105.7 mg g–1. X-ray fluorescence was used to evaluate the amount of U(VI) ions on the resin sample before and after the adsorption.
About the authors
A. Massoud
Cyclotron Facility, Nuclear Research Center
Author for correspondence.
Email: ayman_mass@yahoo.com
Egypt, Cairo
S. A. Waly
Accelerators Department
Email: ayman_mass@yahoo.com
Egypt, Cairo
F. Abou El-Nour
Nuclear Chemistry Department
Email: ayman_mass@yahoo.com
Egypt, Cairo
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