Radiochemical signature of radium-isotopes and some radiological hazard parameters in TENORM waste associated with petroleum production: A review study

Afifi, E. M. El; Mansy, Muhammad S.; Hilal, M.A.

doi:10.1016/j.jenvrad.2022.107042

Cited by 9 publications

(5 citation statements)

References 54 publications

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“…The detector has been calibrated for energy and efficiency to easily calculate the radioactivity of both cesium and strontium. The radioactivity level of the radioactive waste sample was determined by the following equation given by Hilal et al ( 2022 ) and El Afifi et al ( 2023 ) as …”

Section: Resultsmentioning

confidence: 99%

Elaboration and characterization of molybdenum titanium tungsto-phosphate towards the decontamination of radioactive liquid waste from 137 Cs and 85Sr

Abdel-Galil,

Kasem,

Mahrous

2023

Environ Sci Pollut Res

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The crystalline phase of molybdenum titanium tungsto-phosphate (MoTiWPO4) as an inorganic sorbent material was synthesized via the sol–gel method. The physicochemical characteristics of MoTiWPO4 were evaluated by using Fourier transform infrared (FT-IR), scanning electron microscope (SEM), energy dispersive X-ray (EDX), thermal analysis (TGA-DTA), and X-ray diffraction (XRD). MoTiWPO4 sorbent material exhibits a high chemical resistance to HNO3, HCl, and alkaline media. MoTiWPO4 has good thermal stability as it retained about 75.63% of its saturation capacity upon heating at 500 °C. The sorption studies for several metal ions revealed marked high sorption efficiency of MoTiWPO4 towards Cs+ and Sr2+ ions which reached 99% and 95%, respectively. The saturation capacity of MoTiWPO4 for Cs+ and Sr2+ is 113 and 109 mg/g, respectively. MoTiWPO4 is approved to be successfully eliminating both 137Cs and 85Sr from liquid radioactive waste streams by %eff. of 92.5 and 90.3, respectively, in the presence of competing ions from 60Co(divalent) and 152Eu (trivalent), confirming the batch experiment results for the removal of Cs+ and Sr2+ metal ions. Furthermore, the decontamination factor exceeds 13.3 in the case of 137Cs and 10.3 for 85Sr.

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Section: Resultsmentioning

confidence: 99%

Elaboration and characterization of molybdenum titanium tungsto-phosphate towards the decontamination of radioactive liquid waste from 137 Cs and 85Sr

Abdel-Galil,

Kasem,

Mahrous

2023

Environ Sci Pollut Res

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“… where A f and A p are the 134,137 Cs radioactivity-level for feed and permeate, respectively. The activity of the feed and permeate solution can be calculated (El Afifi et al 2023 ; Hilal et al 2022 ) as follows: in which ( A ) is the radioactivity level (Bq/L), t is the counting time, ε is the detector efficiency, I γ is the probability of emission of each gamma ray, and V is the sample volume in (L).…”

Section: Methodsmentioning

confidence: 99%

A prototype system for the removal of 137Cs from liquid radioactive waste using reverse osmosis membrane

Shaltout,

Kandil,

El-Tabl

et al. 2024

Environ Sci Pollut Res

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Cesium removal from aqueous solutions of radioactive waste streams is a challenge in the field of radioactive waste management; this is due to the small atomic radii of Cs+ metal ions and their high migration ability. So, the development of a withstand system for the removal of Cs+ is crucial. In the current study, the removal of radioactive cesium from aqueous solutions using an RO-TLC membrane was studied. Two modifications were conducted; the first is to enlarge the cesium metal ion radii by interacting with mono- and dibasic acids, namely, stearic acid, tartaric acid, citric acid, and EDTA, and the second is the modification of the RO membrane pore size via reaction with the same acids. The modification was confirmed using SEM, FTIR, and EDX analysis techniques. The Cs+ and K+ rejection capacities and water permeability across the membrane at 1.5 bars were evaluated. Along with using the above-mentioned acids, the Cs+ metal ion retention index (RCs) was also obtained. It was found that employing EDTA as a chelating agent in an amount of 1.5 g/L in conjunction with the variation of feed content since it provided the highest value of RCs ~ 98% when used. Moreover, the elution of Cs+ using water, EDTA, ammonia, and HCl is also investigated. The optimal value of the eluent concentration was (0.25 M) HCl. Finally, Langmuir and Freundlich isotherm models were applied for a better understanding of the sorption process. The results of the present work more closely match the Langmuir isotherm model to determine the dominance of the chemical sorption mechanism.

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“…(2) Where Af and Ap are the 134,137 Cs radioactivity-level for feed and permeate, respectively. The activity of the feed and permeate solution can be calculated following (El Afifi et al, 2023;Hilal et al, 2022) as:…”

Section: Radioactive Filtration Experimentsmentioning

confidence: 99%

A prototype system for the removal of 137 Cs from liquid radioactive waste using reverse osmosis membrane

Shaltout,

kandil,

El-Tabl

et al. 2024

Preprint

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Cesium removal from aqueous solutions of radioactive waste streams is a challenge in the field of radioactive waste management; this is due to the small atomic radii of Cs+ metal ions and their high migration ability. So, the development of a withstand system for the removal of Cs+ is crucial, in the current study, the removal of radioactive cesium from aqueous solutions using an RO-TLC membrane was studied. Two modifications were conducted; the first is to enlarge the cesium metal ion radii by interacting with mono and dia basic acids namely, stearic acid, tartaric acid, citric acid, and EDTA, and the second is the modification of the RO-membrane pore size via reaction with the same acids. The modification was confirmed using SEM, FTIR, and EDX analysis techniques. The Cs+ and K+ rejection capacities and water permeability across the membrane at 1.5 bars were evaluated. Along with using the above-mentioned acids, the Cs+ metal ion retention index (RCs) was also obtained. It was found that employing EDTA as a chelating agent in an amount of 1.5 g/L in conjunction with the variation of feed content since it provided the highest value of RCs ~98% when used. Moreover, the elution of Cs+ using; water, EDTA, Ammonia, and HCl is also investigated. The optimal value of the eluent concentration was (0.25 M) HCl. Finally, Langmuir and Freundlich isotherm models were applied for better understanding of the sorption process. Results shows that the present work results are more fitted to Langmuir isotherm model determine the dominance of the chemical sorption mechanism.

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Radiochemical signature of radium-isotopes and some radiological hazard parameters in TENORM waste associated with petroleum production: A review study

Cited by 9 publications

References 54 publications

Elaboration and characterization of molybdenum titanium tungsto-phosphate towards the decontamination of radioactive liquid waste from 137 Cs and 85Sr

Elaboration and characterization of molybdenum titanium tungsto-phosphate towards the decontamination of radioactive liquid waste from 137 Cs and 85Sr

A prototype system for the removal of 137Cs from liquid radioactive waste using reverse osmosis membrane

A prototype system for the removal of 137 Cs from liquid radioactive waste using reverse osmosis membrane

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