Removal of U(VI) from simulated liquid waste using synthetic organic resin

被引：15

作者：

Massoud A. ^{[1
]}

Waly S.A. ^{[2
]}

Abou El-Nour F. ^{[3
]}

机构：

[1] Cyclotron Facility, Nuclear Research Center, Atomic Energy Authority, P.O. Box 13759, Cairo

[2] Accelerators Department, Nuclear Research Center, Atomic Energy Authority, P.O. Box 13759, Cairo

[3] Nuclear Chemistry Department, Hot Laboratories Center, Atomic Energy Authority, P.O. Box 13759, Cairo

来源：

Radiochemistry | 2017年 / 59卷 / 3期

关键词：

nuclear fuel fabrication; organic resin; uranium removal; waste treatment;

D O I：

10.1134/S1066362217030092

中图分类号：

学科分类号：

摘要：

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. © 2017, Pleiades Publishing, Inc.

引用

页码：272 / 279

页数：7