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A Technical Guide for Performing Spectroscopic Measurements on Metal-Organic Frameworks
Published on: April 28, 2023
A comprehensive study for the potential removal of 152+154Eu radionuclides using a promising modified strontium-based
Reda R Sheha1, Sheta M Sheta2, Mohamed A Hamouda3
1Nuclear Chem. Dept., Hot Lab Center, Egyptian Atomic Energy Authority, P. O. 13759, Cairo, Egypt.
Abstract:
A facile modification of a strontium-based MOF using oxalic acid was carried out to prepare MTSr-OX MOF, which was used as a potential substance for eliminating 152+154Eu radioisotopes. Various analytical techniques were used to characterize MTSr-OX-MOF. The prepared MOF had a rod-like structure with a BET surface area of 101.55 m2 g-1. Batch sorption experiments were used to investigate the sorption performance of MTSr-OX-MOF towards 152+154Eu radionuclides where different parameters like pH, contact time, initial 152+154Eu concentration, ionic strength, and temperature were scrutinized to determine the optimum conditions for 152+154Eu removal. MTSr-OX-MOF showed superior effectiveness in the elimination of 152+154Eu with a maximum sorption capacity of 234.72 mg g-1 at pH 3.5. Kinetics fitted with the pseudo-second-order model and the Langmuir model correctly described the sorption mechanism. The thermodynamic variables were carefully examined, demonstrating that the 152+154Eu sorption was endothermic as well as spontaneous. The MTSr-OX-MOF has been found to be a significantly more effective sorbent towards 152+154Eu than that of many other adsorbents. When applied to real active waste, MTSr-OX-MOF demonstrated excellent removal performance for a wide range of radionuclides. As a result, the MTSr-OX-MOF can be recognized as an attractive solution for the 152+154Eu purification from active waste.
Insights
A modified strontium-based metal-organic framework (MOF), MTSr-OX MOF, effectively removes europium-152/154 (Eu) radioisotopes. This novel material shows high sorption capacity and potential for purifying radioactive waste.
Area of Science:
- Materials Science
- Radiochemistry
- Environmental Science
Background:
- Radioactive waste management poses challenges due to the presence of hazardous radioisotopes like Europium-152/154 (Eu).
- Developing efficient sorbent materials is crucial for the safe disposal and remediation of nuclear waste.
- Metal-organic frameworks (MOFs) offer tunable properties for selective radionuclide removal.
Purpose of the Study:
- To synthesize and characterize a modified strontium-based MOF (MTSr-OX MOF) for the removal of 152+154Eu radioisotopes.
- To investigate the sorption performance and mechanism of MTSr-OX MOF under various experimental conditions.
- To evaluate the potential of MTSr-OX MOF as a sorbent for radioactive waste remediation.
Main Methods:
- Facile modification of a strontium-based MOF using oxalic acid to create MTSr-OX MOF.
- Characterization of MTSr-OX MOF using various analytical techniques, including BET surface area analysis.
- Batch sorption experiments to study the removal of 152+154Eu, optimizing parameters such as pH, contact time, initial concentration, ionic strength, and temperature.
Main Results:
- MTSr-OX MOF exhibited a rod-like structure with a BET surface area of 101.55 m² g⁻¹.
- The material demonstrated superior effectiveness in eliminating 152+154Eu, achieving a maximum sorption capacity of 234.72 mg g⁻¹ at pH 3.5.
- Sorption kinetics followed a pseudo-second-order model, and the Langmuir model described the sorption mechanism, indicating endothermic and spontaneous processes.
Conclusions:
- MTSr-OX MOF is a highly effective sorbent for 152+154Eu removal, outperforming many existing adsorbents.
- The material shows excellent performance in removing a broad range of radionuclides from real active waste.
- MTSr-OX MOF presents an attractive and efficient solution for the purification of 152+154Eu from radioactive waste streams.

