Synthesis and sorption potential study of Al2O3ZrO2CeO2 composite material for removal of some radionuclides from radioactive waste effluent

Increasing in the use of various radioactive elements in many applications over the past few decades has accompanied with an increase radioactive waste. Therefore, preparation of Al2O3ZrO2CeO2 nanocomposite material by sol-gel polymeric method is carried out. The nanocomposite material was character...

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Bibliographic Details
Published in:Applied radiation and isotopes 2019-05, Vol.147, p.40-47
Main Authors: Attallah, M.F., Hassan, H.S., Youssef, M.A.
Format: Article
Language:English
Subjects:
Artificial radionuclides
Cesium & Strontium
Kinetic model
Nanomaterials
Removal
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Summary:Increasing in the use of various radioactive elements in many applications over the past few decades has accompanied with an increase radioactive waste. Therefore, preparation of Al2O3ZrO2CeO2 nanocomposite material by sol-gel polymeric method is carried out. The nanocomposite material was characterized by some analytical techniques such as Fourier transform infrared (FTIR), Thermograviemtric & differential thermal analysis (TGA & DTA), X-ray diffraction (XRD) and scanning electron microscopy (SEM). Separation of 134Cs and 90Sr/90Y as a fission product present in radioactive waste effluents using the prepared nanocomposite was investigated. The result showed that removal of 94%, 44% and 8.5% for 134Cs, 90Sr and 90Y, respectively. The experimental results are fitted with pseudo-second-order kinetic model. Isotherm models of sorption process are calculated and it can be concluded that the Langmuir model more fitted than Freundlich model. The calculated thermodynamic functions exhibited that sorption behavior of 134Cs and 90Sr ions are spontaneous in nature and the positive value of ΔHo value indicates that the sorption is endothermic. The results demonstrated that the % sorption of 134Cs(I) and 90Sr(II) is sharply decreased in the presence of coexisting ions (Na, Mg and Cr) using nanoparticles of Al2O3 ZrO2CeO2. •Nuclear facilities operations are generating a large volume of low level liquid radioactive waste.•Treatment of radioactive waste has a great of attention to avoid discharged any radionuclides in environment.•Removal of some radionuclides from radioactive waste effluent using new synthetic composite material.
ISSN:0969-8043
1872-9800
DOI:10.1016/j.apradiso.2019.01.015