Deepika Nair, Prema Gireesan, Dayamoy Banerjee, Raman K. Mishra, Sanjay Kumar
This paper reports the studies carried out on the development of a process for the recovery of 1,3-dioctyloxycalix[4]arene-18-crown-6 (CC-6) from the spent solvent generated during industrial scale separation of 137Cs from High Level Liquid Waste (HLLW). Initial works involved the validation of a conceptual process design and optimization of the process parameters with a simulated solvent. The optimized process was then tested with actual spent solvent to recover calix-crown-6. Such a process to recover undegraded and potentially re-usable calix-crown-6 from the spent solvent has been attempted for the first time with the aim of value recovery and reduced spent solvent management burden.
{"title":"Process development studies on the recovery of caesium specific calix-crown-6 extractant from actual spent calix solution for efficient spent solvent management","authors":"Deepika Nair, Prema Gireesan, Dayamoy Banerjee, Raman K. Mishra, Sanjay Kumar","doi":"10.1515/ract-2023-0192","DOIUrl":"https://doi.org/10.1515/ract-2023-0192","url":null,"abstract":"This paper reports the studies carried out on the development of a process for the recovery of 1,3-dioctyloxycalix[4]arene-18-crown-6 (CC-6) from the spent solvent generated during industrial scale separation of <jats:sup>137</jats:sup>Cs from High Level Liquid Waste (HLLW). Initial works involved the validation of a conceptual process design and optimization of the process parameters with a simulated solvent. The optimized process was then tested with actual spent solvent to recover calix-crown-6. Such a process to recover undegraded and potentially re-usable calix-crown-6 from the spent solvent has been attempted for the first time with the aim of value recovery and reduced spent solvent management burden.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-06-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141503022","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Hemn Salh, S. Sedeeq, Serpil Aközcan Pehlivanoğlu, Ikbal M. Albarzinji, F. Külahcı
Abstract In this study, the activity concentration of artificial and natural radionuclides such as 137Cs, 40K, 226Ra, and 232Th was measured in the soil under the roots; leaves; and fruits of six different fruit trees namely mulberry, fig, apricot, olive, black and white grapes in Koya district, Erbil province, Iraq. For this purpose, a high-resolution gamma spectroscopy consisting of a high-purity germanium (HPGe) detector was used. In addition, the associated radiological risks from soil and fruits were assessed by calculating several radiological indices such as radium equivalent (Raeq.s), absorbed dose (Ds), indoor (AEDEs indoor ) and outdoor annual effective doses (AEDEs outdoor ), internal and external hazard indices, gamma index and the excess lifetime cancer risk (ELRCs). The results show that consuming these fruits is radiologically safe because they can cause an annual effective dose of about 61.72 μSv y−1 and excess lifetime cancer risk of 0.06 × 10−3 Sv y−1. On the other hand, transfer factors of radionuclides from soil to leaves; and from soil to fruits were studied. The transfer factor analysis revealed that among the studied fruits and radionuclides, apricot and mulberry exhibited the highest transfer factors for 40K, with values of 1.85 and 1.87, respectively.
{"title":"On transfer factors of natural radionuclides and radiological health risks assessment of some fruit samples","authors":"Hemn Salh, S. Sedeeq, Serpil Aközcan Pehlivanoğlu, Ikbal M. Albarzinji, F. Külahcı","doi":"10.1515/ract-2023-0233","DOIUrl":"https://doi.org/10.1515/ract-2023-0233","url":null,"abstract":"Abstract In this study, the activity concentration of artificial and natural radionuclides such as 137Cs, 40K, 226Ra, and 232Th was measured in the soil under the roots; leaves; and fruits of six different fruit trees namely mulberry, fig, apricot, olive, black and white grapes in Koya district, Erbil province, Iraq. For this purpose, a high-resolution gamma spectroscopy consisting of a high-purity germanium (HPGe) detector was used. In addition, the associated radiological risks from soil and fruits were assessed by calculating several radiological indices such as radium equivalent (Raeq.s), absorbed dose (Ds), indoor (AEDEs indoor ) and outdoor annual effective doses (AEDEs outdoor ), internal and external hazard indices, gamma index and the excess lifetime cancer risk (ELRCs). The results show that consuming these fruits is radiologically safe because they can cause an annual effective dose of about 61.72 μSv y−1 and excess lifetime cancer risk of 0.06 × 10−3 Sv y−1. On the other hand, transfer factors of radionuclides from soil to leaves; and from soil to fruits were studied. The transfer factor analysis revealed that among the studied fruits and radionuclides, apricot and mulberry exhibited the highest transfer factors for 40K, with values of 1.85 and 1.87, respectively.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141375027","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
N. Moulai, Brahim Beladel, Mohammed Messaoudi, Nadjet Osmani, Abdelkarim Brahimi, Abderrahim Malki, Rahima Lammouri, Abdelkader Ouanezar
Abstract This study represents the investigation of major and trace elements in two indigenous plants, Cynodon dactylon (L.) and Phragmites australis, grown in the Ghardaia region of Southern Algeria. Using Instrumental Neutron Activation Analysis (INAA) technique, the research aimed to ascertain the content of essential and toxic elements in the aerial parts of these plants. Twenty eight elements as (Ag, As, Ba, Br, Ca, Ce, Co, Cr, Cs, Eu, Fe, Hf, Hg, K, La, Lu, Na, Nd, Rb, Sb, Sc, Se, Sm, Sr, Tb, Th, Yb and Zn) were analysis with INAA method. Given the scarcity of data regarding essential and toxic chemical elements in food within Algeria, the study focused on evaluating the content of these elements in two plant species commonly utilized by Bedouins in traditional medicine and as fodder, as well as by professionals for decontamination and water purification purposes. The concentrations of mineral elements observed in these plants were found to be in proximity to the minimum levels recommended by the Food and Agriculture Organization (FAO). The data obtained from this investigation are deemed applicable for Algerian food purposes, offering valuable insights into the elemental composition of these plants and their potential roles in traditional and practical applications.
{"title":"Application of INAA technique for analysis of essential and toxic elements in two Algerian plants Cynodon dactylon L. and Phragmites australis","authors":"N. Moulai, Brahim Beladel, Mohammed Messaoudi, Nadjet Osmani, Abdelkarim Brahimi, Abderrahim Malki, Rahima Lammouri, Abdelkader Ouanezar","doi":"10.1515/ract-2023-0270","DOIUrl":"https://doi.org/10.1515/ract-2023-0270","url":null,"abstract":"Abstract This study represents the investigation of major and trace elements in two indigenous plants, Cynodon dactylon (L.) and Phragmites australis, grown in the Ghardaia region of Southern Algeria. Using Instrumental Neutron Activation Analysis (INAA) technique, the research aimed to ascertain the content of essential and toxic elements in the aerial parts of these plants. Twenty eight elements as (Ag, As, Ba, Br, Ca, Ce, Co, Cr, Cs, Eu, Fe, Hf, Hg, K, La, Lu, Na, Nd, Rb, Sb, Sc, Se, Sm, Sr, Tb, Th, Yb and Zn) were analysis with INAA method. Given the scarcity of data regarding essential and toxic chemical elements in food within Algeria, the study focused on evaluating the content of these elements in two plant species commonly utilized by Bedouins in traditional medicine and as fodder, as well as by professionals for decontamination and water purification purposes. The concentrations of mineral elements observed in these plants were found to be in proximity to the minimum levels recommended by the Food and Agriculture Organization (FAO). The data obtained from this investigation are deemed applicable for Algerian food purposes, offering valuable insights into the elemental composition of these plants and their potential roles in traditional and practical applications.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141372764","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Si-yi Gong, Jinguang Zheng, Xin Yang, Yan Ma, Zhenfeng Tong, Tao Chen
Abstract Radionuclide migration is an essential process in the performance and safety assessments of radioactive waste repository. This study investigates uranium migration in Beishan granite using the continuous column method, focusing on the effects of flow rate, eluent pH, and carbonate. Experimental parameters were used to perform COMSOL simulations of the migration process. The findings reveal that mechanical dispersion plays a predominant role in uranium migration in the granite column. Notably, the impact of adsorption on migration appears to be limited, likely due to the brief contact time in the experimental setup. The study successfully demonstrates the capability of COMSOL in simulating radionuclide migration, offering significant insights for the performance and safety assessments of repository.
{"title":"Migration study of uranium in Beishan granite by the continuous column method","authors":"Si-yi Gong, Jinguang Zheng, Xin Yang, Yan Ma, Zhenfeng Tong, Tao Chen","doi":"10.1515/ract-2024-0281","DOIUrl":"https://doi.org/10.1515/ract-2024-0281","url":null,"abstract":"Abstract Radionuclide migration is an essential process in the performance and safety assessments of radioactive waste repository. This study investigates uranium migration in Beishan granite using the continuous column method, focusing on the effects of flow rate, eluent pH, and carbonate. Experimental parameters were used to perform COMSOL simulations of the migration process. The findings reveal that mechanical dispersion plays a predominant role in uranium migration in the granite column. Notably, the impact of adsorption on migration appears to be limited, likely due to the brief contact time in the experimental setup. The study successfully demonstrates the capability of COMSOL in simulating radionuclide migration, offering significant insights for the performance and safety assessments of repository.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-06-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141385992","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A. M. Emara, Emad M. Elsharma, I. M. Abdelmonem, Mamdoh R. Mahmoud
A novel SiO2/Al2O3/poly(acrylic acid-co-glycidyl methacrylate), SiO2/Al2O3/P(AA-co-GMA), composite was synthesized and evaluated for its effectiveness in adsorbing Co(II) ions from aqueous solutions. The composite was analyzed using various techniques including FTIR, SEM, TGA, DTA, and XRD. The composite displays a high specific surface area of 17.451 m2/g, exceeding that of the corresponding copolymer, which measures 0.236 m2/g. Batch adsorption experiments were conducted to investigate the factors influencing the adsorption capacity of the composite for Co(II) ions. In the pH experiments, it was found that at a solution pH of 3.4, the P(AA-co-GMA) copolymer alone showed limited capability in adsorbing Co(II) ions, achieving only 3.82 mg/g. However, upon integration of SiO2/Al2O3 into the polymer matrix, the composite exhibited a significantly enhanced adsorption capacity of 103.54 mg/g. The adsorption process followed a pseudo-second-order kinetic model and attained equilibrium within 60 min. The Langmuir isotherm model was found to best describe the adsorption behavior, with a maximum adsorption capacity of 217.86 mg/g. The adsorption of Co(II) was significantly affected by the ionic strength, especially with Al3+ displaying a more pronounced impact on the adsorption of Co(II) ions compared to Na+, Ca2+, and Mg2+. Thermodynamic studies indicate that the adsorption process was spontaneous and endothermic. Overall, the SiO2/Al2O3/P(AA-co-GMA) composite material displayed significant adsorption ability for Co(II) ions, making it a suitable option for further development as an effective adsorbent in water treatment applications.
{"title":"Evaluating SiO2/Al2O3/poly(acrylic acid-co-glycidyl methacrylate) composite as a novel adsorbent for cobalt(II) radionuclides","authors":"A. M. Emara, Emad M. Elsharma, I. M. Abdelmonem, Mamdoh R. Mahmoud","doi":"10.1515/ract-2023-0243","DOIUrl":"https://doi.org/10.1515/ract-2023-0243","url":null,"abstract":"\u0000 A novel SiO2/Al2O3/poly(acrylic acid-co-glycidyl methacrylate), SiO2/Al2O3/P(AA-co-GMA), composite was synthesized and evaluated for its effectiveness in adsorbing Co(II) ions from aqueous solutions. The composite was analyzed using various techniques including FTIR, SEM, TGA, DTA, and XRD. The composite displays a high specific surface area of 17.451 m2/g, exceeding that of the corresponding copolymer, which measures 0.236 m2/g. Batch adsorption experiments were conducted to investigate the factors influencing the adsorption capacity of the composite for Co(II) ions. In the pH experiments, it was found that at a solution pH of 3.4, the P(AA-co-GMA) copolymer alone showed limited capability in adsorbing Co(II) ions, achieving only 3.82 mg/g. However, upon integration of SiO2/Al2O3 into the polymer matrix, the composite exhibited a significantly enhanced adsorption capacity of 103.54 mg/g. The adsorption process followed a pseudo-second-order kinetic model and attained equilibrium within 60 min. The Langmuir isotherm model was found to best describe the adsorption behavior, with a maximum adsorption capacity of 217.86 mg/g. The adsorption of Co(II) was significantly affected by the ionic strength, especially with Al3+ displaying a more pronounced impact on the adsorption of Co(II) ions compared to Na+, Ca2+, and Mg2+. Thermodynamic studies indicate that the adsorption process was spontaneous and endothermic. Overall, the SiO2/Al2O3/P(AA-co-GMA) composite material displayed significant adsorption ability for Co(II) ions, making it a suitable option for further development as an effective adsorbent in water treatment applications.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-06-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141266642","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nancy Moreno-Gil, Verónica E. Badillo-Almaraz, Guadalupe C. Velazquez-Peña, Miguel A. Camacho-López, Keila Issac-Olivé
In order to contribute to the sufficient supply of clinical 99mTc(VII), the sorption behavior of neutron-produced 99Mo(VI) was investigated on synthetized single and binary Ti and Zr xerogels treated at different temperatures, under normal operating conditions. Materials were prepared by the sol–gel method and characterized by several techniques. Sorption batch systems were performed using 99Mo radiotracer to determine the metallic affinity as a function of pH, and a methodology was developed in order to obtain the maximum capacities by surface saturation, where the Ti-388, TiZr-388 (3:1) and Zr-388 samples showed the most noteworthy sorption behaviors (33.1 ± 0.34 mg/g at pH ∼ 6.0, 31.7 ± 0.27 mg/g at pH ∼ 6.5, and 23.5 ± 0.61 mg/g at pH ∼ 6.8, respectively). The molybdenum-99 sorption behavior was also studied by fitting to the Freundlich and Langmuir models, and all xerogels could be described as heterogeneous materials with favorable 99Mo sorption properties. Finally, preliminary studies of clinical-scale 99Mo/99mTc generators were performed, the results revealed the next maximum 99mTc elution yield order Ti-388 (89.6 %) > TiZr-388 (3:1) (86.7 %) > Zr-388 (77.7 %).
{"title":"Sorption behavior of low specific activity 99Mo on Ti- and Zr-xerogels as an alternative to fission-based 99Mo/99mTc generators","authors":"Nancy Moreno-Gil, Verónica E. Badillo-Almaraz, Guadalupe C. Velazquez-Peña, Miguel A. Camacho-López, Keila Issac-Olivé","doi":"10.1515/ract-2023-0223","DOIUrl":"https://doi.org/10.1515/ract-2023-0223","url":null,"abstract":"In order to contribute to the sufficient supply of clinical <jats:sup>99m</jats:sup>Tc(VII), the sorption behavior of neutron-produced <jats:sup>99</jats:sup>Mo(VI) was investigated on synthetized single and binary Ti and Zr xerogels treated at different temperatures, under normal operating conditions. Materials were prepared by the sol–gel method and characterized by several techniques. Sorption batch systems were performed using <jats:sup>99</jats:sup>Mo radiotracer to determine the metallic affinity as a function of pH, and a methodology was developed in order to obtain the maximum capacities by surface saturation, where the Ti-388, TiZr-388 (3:1) and Zr-388 samples showed the most noteworthy sorption behaviors (33.1 ± 0.34 mg/g at pH ∼ 6.0, 31.7 ± 0.27 mg/g at pH ∼ 6.5, and 23.5 ± 0.61 mg/g at pH ∼ 6.8, respectively). The molybdenum-99 sorption behavior was also studied by fitting to the Freundlich and Langmuir models, and all xerogels could be described as heterogeneous materials with favorable <jats:sup>99</jats:sup>Mo sorption properties. Finally, preliminary studies of clinical-scale <jats:sup>99</jats:sup>Mo/<jats:sup>99m</jats:sup>Tc generators were performed, the results revealed the next maximum <jats:sup>99m</jats:sup>Tc elution yield order Ti-388 (89.6 %) > TiZr-388 (3:1) (86.7 %) > Zr-388 (77.7 %).","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-05-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141189247","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Monitoring radioactivity around nuclear power plants is important to avoid the risks of radiation. This study provides an overview of the radioactive emission impact on the near surroundings of the Metsamor nuclear power plant in Armenia. In this context, 29 soil samples were collected from the 40, 80, 120, 160 km radius areas determined in the direction of Iğdır province by accepting the Metsamor nuclear power plant as the center. The activity concentrations of 226Ra, 232Th, 40K and 137Cs in soil samples ranged from 7.90 to 23.44, 7.11 to 33.55, 132.54 to 502.69 and 0.33 to 17.61 Bq/kg, respectively. In addition, the radioactivity concentrations in some agricultural products and the transfer factors from soil to plant were determined. As a result, there is no significant radiological risk in terms of studied radioisotopes for people living in this region.
{"title":"Investigation of radioactivity concentrations and soil-to-plant transfer factors in soil samples taken from different distance zones to the Metsamor nuclear power plant","authors":"Serdar Dizman, Selim Sari, Cafer Mert Yesilkanat","doi":"10.1515/ract-2024-0291","DOIUrl":"https://doi.org/10.1515/ract-2024-0291","url":null,"abstract":"Monitoring radioactivity around nuclear power plants is important to avoid the risks of radiation. This study provides an overview of the radioactive emission impact on the near surroundings of the Metsamor nuclear power plant in Armenia. In this context, 29 soil samples were collected from the 40, 80, 120, 160 km radius areas determined in the direction of Iğdır province by accepting the Metsamor nuclear power plant as the center. The activity concentrations of <jats:sup>226</jats:sup>Ra, <jats:sup>232</jats:sup>Th, <jats:sup>40</jats:sup>K and <jats:sup>137</jats:sup>Cs in soil samples ranged from 7.90 to 23.44, 7.11 to 33.55, 132.54 to 502.69 and 0.33 to 17.61 Bq/kg, respectively. In addition, the radioactivity concentrations in some agricultural products and the transfer factors from soil to plant were determined. As a result, there is no significant radiological risk in terms of studied radioisotopes for people living in this region.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-05-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141189493","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Sara S. Mahrous, Muhammad S. Mansy, Maha A. Youssef
The application of Phalaris seed peel (PSP) for the production of biochar involves the pyrolysis process in an N2 environment, resulting in the creation of a cost-effective sorbent. Two distinct modifications were conducted on the existing biochar (BC), employing just silicate (BC/SiO2) and in combination with iron-silicate (BC/SiO2/Fe). Several analytical methods were used to look at the modified biochar’s physical and chemical properties. These included scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDX), X-ray diffraction (XRD), Fourier-transform infrared spectroscopy (FTIR), thermogravimetric analysis-differential thermal analysis (TGA-DTA), and surface area analysis. Based on the initial investigations, it has been revealed that the use of silica and iron as the second modification is a more suitable approach for effectively retaining 133Ba from liquid radioactive waste streams. The investigation of sorption kinetics and isotherms was conducted to enhance our understanding of the process. The Langmuir isotherm model demonstrates the most optimal correlation for sorption, yielding a maximum sorption capacity (Qmax) of 31 mg/g. Furthermore, an evaluation was performed on the BC/SiO2/Fe sorbent material by subjecting it to a mixture of simulated radioactive liquid waste, which included 133Ba, 60Co, and 137Cs.The experimental results indicate that BC/SiO2/Fe exhibits a comparatively higher sorption capacity for 133Ba when compared to 60Co and 137Cs as competing ions.
{"title":"The performance of iron-silicate-based biochar as a sorbent material towards 133Ba retention from radioactive liquid waste","authors":"Sara S. Mahrous, Muhammad S. Mansy, Maha A. Youssef","doi":"10.1515/ract-2024-0273","DOIUrl":"https://doi.org/10.1515/ract-2024-0273","url":null,"abstract":"The application of Phalaris seed peel (PSP) for the production of biochar involves the pyrolysis process in an N<jats:sub>2</jats:sub> environment, resulting in the creation of a cost-effective sorbent. Two distinct modifications were conducted on the existing biochar (BC), employing just silicate (BC/SiO<jats:sub>2</jats:sub>) and in combination with iron-silicate (BC/SiO<jats:sub>2</jats:sub>/Fe). Several analytical methods were used to look at the modified biochar’s physical and chemical properties. These included scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDX), X-ray diffraction (XRD), Fourier-transform infrared spectroscopy (FTIR), thermogravimetric analysis-differential thermal analysis (TGA-DTA), and surface area analysis. Based on the initial investigations, it has been revealed that the use of silica and iron as the second modification is a more suitable approach for effectively retaining <jats:sup>133</jats:sup>Ba from liquid radioactive waste streams. The investigation of sorption kinetics and isotherms was conducted to enhance our understanding of the process. The Langmuir isotherm model demonstrates the most optimal correlation for sorption, yielding a maximum sorption capacity (<jats:italic>Q</jats:italic> <jats:sub>max</jats:sub>) of 31 mg/g. Furthermore, an evaluation was performed on the BC/SiO<jats:sub>2</jats:sub>/Fe sorbent material by subjecting it to a mixture of simulated radioactive liquid waste, which included <jats:sup>133</jats:sup>Ba, <jats:sup>60</jats:sup>Co, and <jats:sup>137</jats:sup>Cs.The experimental results indicate that BC/SiO<jats:sub>2</jats:sub>/Fe exhibits a comparatively higher sorption capacity for <jats:sup>133</jats:sup>Ba when compared to <jats:sup>60</jats:sup>Co and <jats:sup>137</jats:sup>Cs as competing ions.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141165985","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
U. K. Maity, Namitha Janardhanan, Manoravi Periasamy
Estimation of Zr in fresh and irradiated metal alloy fuel is important. The homogeneous dissolver solution represents the fuel composition better compared to a highly heterogeneous solid pellet. The present study employs LIBS to determine Zr in the simulated dissolver solution. Four different compositions of U–Zr samples where the Zr/U ratio varies from 0.04 to 0.18 % are analyzed by LIBS with an in-house designed liquid sample cell. A good correlation coefficient is achieved for the measurements in the calibration plot. The results for identifying non-overlapping peaks, calibration plot, precision, deviation, and detection limit are discussed in detail. Two set of solid samples, an oxide pellet and metal alloy with similar Zr/U composition, are also analyzed by LIBS. The results obtained from these three set of samples are inter-compared, and the reason for getting a better Zr/U intensity ratio for a dried coating of sample on aluminium for a given composition is explained.
{"title":"Quantification of Zr in simulated dissolver solution of U–Zr fuel by laser-induced breakdown spectroscopy","authors":"U. K. Maity, Namitha Janardhanan, Manoravi Periasamy","doi":"10.1515/ract-2023-0208","DOIUrl":"https://doi.org/10.1515/ract-2023-0208","url":null,"abstract":"\u0000 Estimation of Zr in fresh and irradiated metal alloy fuel is important. The homogeneous dissolver solution represents the fuel composition better compared to a highly heterogeneous solid pellet. The present study employs LIBS to determine Zr in the simulated dissolver solution. Four different compositions of U–Zr samples where the Zr/U ratio varies from 0.04 to 0.18 % are analyzed by LIBS with an in-house designed liquid sample cell. A good correlation coefficient is achieved for the measurements in the calibration plot. The results for identifying non-overlapping peaks, calibration plot, precision, deviation, and detection limit are discussed in detail. Two set of solid samples, an oxide pellet and metal alloy with similar Zr/U composition, are also analyzed by LIBS. The results obtained from these three set of samples are inter-compared, and the reason for getting a better Zr/U intensity ratio for a dried coating of sample on aluminium for a given composition is explained.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141102039","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"化学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
M. Sayyed, Aljawhara H. Almuqrin, Karem A. Mahmoud
The current work seeks to develop a novel CuO-doped lead calcium barium borate glass using the melt quenching method at 1100 °C. There was a 3.91–4.49 g/cm3 change in the fabricated glasses’ density, with a respective 0–15 mol.% increase in the CuO concentration. Additionally, substituting CuO for B2O3 reduced the fabricated glasses mechanical properties due to the decreased dissociation energy between 63.99 and 60.50 kcal/cm3, and the packing factor decreased between 15.22 and 13.23 cm3/mol. Through increasing the fabricated glasses’ CuO concentration, there was a decrease in the bulk, longitudinal, shear, and mechanical Young moduli. Moreover, Monte Carlo simulation (energy interval: 0.033–2.506 MeV) was employed to evaluate the fabricated glasses’ ability to shield gamma rays. A 0–15 mol.% increase in the CuO concentration raised the linear attenuation coefficient (LAC) between 14.081 and 16.797 cm−1 (0.059 MeV), 0.325–0.371 cm−1 (0.662 MeV), and 0.154–0.176 cm−1 (2.506 MeV). The LAC enhancement reduced the required half value thickness of the fabricated glasses by 16.2 %, 12.53 %, and 12.85 % at the of 0.059, 0.662, and 2.506 MeV gamma ray energies.
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