The aim of this study is to create a radiological map of Kırşehir province in Turkey by analyzing the radioactivity levels of soil samples and environmental radiation measurements. 226Ra, 232Th, 40K and 137Cs radionuclides were analysed in soil samples collected from 47 locations using gamma spectrometry with an HPGe detector. According to the results obtained, gamma radioactivity concentration ranges and mean values for 226Ra, 232Th, 40K and 137Cs were determined as 133 ± 15–1515 ± 128 Bq/kg (599.40 Bq/kg), 0.3 ± 0.09–21.1 ± 1.7 Bq/kg (4.61 Bq/kg), 8.7 ± 0.9–128.5 ± 8.5 Bq/kg (29.66 Bq/kg) and 11.6 ± 8.6–273.8 ± 19.9 Bq/kg (48.80 Bq/kg) respectively. Average radioactivity levels for 40K and 232Th are above the world average. The mean radium equivalent activity (Raeq), gamma dose rate (D), annual effective dose equivalent (AEDE), external hazard index (Hex), and the excess lifetime cancer risk (ELCR) were calculated as 145.45 Bq/kg, 122.13 nGy/h, 0.15 mSv/h, 0.39 and 0.29 × 10−3 respectively.
{"title":"Determination of natural and artificial radioactivity levels and radiation hazard indices for soil samples in Kırşehir","authors":"Sümeyra Yamçıçıer, Doğan Yaşar","doi":"10.1515/ract-2023-0215","DOIUrl":"https://doi.org/10.1515/ract-2023-0215","url":null,"abstract":"The aim of this study is to create a radiological map of Kırşehir province in Turkey by analyzing the radioactivity levels of soil samples and environmental radiation measurements. <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 radionuclides were analysed in soil samples collected from 47 locations using gamma spectrometry with an HPGe detector. According to the results obtained, gamma radioactivity concentration ranges and mean values for <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 were determined as 133 ± 15–1515 ± 128 Bq/kg (599.40 Bq/kg), 0.3 ± 0.09–21.1 ± 1.7 Bq/kg (4.61 Bq/kg), 8.7 ± 0.9–128.5 ± 8.5 Bq/kg (29.66 Bq/kg) and 11.6 ± 8.6–273.8 ± 19.9 Bq/kg (48.80 Bq/kg) respectively. Average radioactivity levels for <jats:sup>40</jats:sup>K and <jats:sup>232</jats:sup>Th are above the world average. The mean radium equivalent activity (Ra<jats:sub>eq</jats:sub>), gamma dose rate (<jats:italic>D</jats:italic>), annual effective dose equivalent (AEDE), external hazard index (<jats:italic>H</jats:italic> <jats:sub> <jats:italic>ex</jats:italic> </jats:sub>), and the excess lifetime cancer risk (ELCR) were calculated as 145.45 Bq/kg, 122.13 nGy/h, 0.15 mSv/h, 0.39 and 0.29 × 10<jats:sup>−3</jats:sup> respectively.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"69 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2023-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529146","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}
Saber Ibrahim, Ahmed M. Masoud, Mahmoud M. El-Maadawy, Hager Fahmy, Mohamed Taha
Plastic packaging waste is considered a serious threat to the environment due to its non-biodegradable nature. Transforming plastic waste into active carbons using pyrolysis methods could be a valuable option to solve the challenge of plastic waste. Synthesized active carbon was differentiated using zeta potential, particle size, SEM, BET, and DSC. This study also investigates the use of obtained active carbons for U(VI) removal from commercial phosphoric acid. The kinetics of adsorption were found to follow the pseudo-second-order model and intra-particle diffusion as one of the controlling mechanisms. Langmuir, and Freundlich, isotherms were employed to explore the equilibrium data. Furthermore, thermodynamic investigations revealed that uranium uptake is an endothermic, feasible, and spontaneous process. The present study concludes that plastic waste-based activated carbon could be employed as a low-cost alternative to commercial activated carbon for uranium removal from phosphoric acid and the production of green fertilizers.
{"title":"Recycling waste polymer packaging materials as effective active carbon porous materials for uranium removal from commercial phosphoric acid","authors":"Saber Ibrahim, Ahmed M. Masoud, Mahmoud M. El-Maadawy, Hager Fahmy, Mohamed Taha","doi":"10.1515/ract-2023-0165","DOIUrl":"https://doi.org/10.1515/ract-2023-0165","url":null,"abstract":"Plastic packaging waste is considered a serious threat to the environment due to its non-biodegradable nature. Transforming plastic waste into active carbons using pyrolysis methods could be a valuable option to solve the challenge of plastic waste. Synthesized active carbon was differentiated using zeta potential, particle size, SEM, BET, and DSC. This study also investigates the use of obtained active carbons for U(VI) removal from commercial phosphoric acid. The kinetics of adsorption were found to follow the pseudo-second-order model and intra-particle diffusion as one of the controlling mechanisms. Langmuir, and Freundlich, isotherms were employed to explore the equilibrium data. Furthermore, thermodynamic investigations revealed that uranium uptake is an endothermic, feasible, and spontaneous process. The present study concludes that plastic waste-based activated carbon could be employed as a low-cost alternative to commercial activated carbon for uranium removal from phosphoric acid and the production of green fertilizers.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"18 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2023-11-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529110","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}
Mohamed Ragab Abass, Maha Ali Youssef, Marwa Ahmed Eid
This work is interested in the sorption and separation of 131Ba, 109Cd, 152+154Eu, and 97Zr from radioactive solutions onto barium molybdenum titanate loaded on carboxy methyl cellulose (BaMoTi@CMC) composites. In this work, different samples of BaMoTi@CMC composites were fabricated by the co-precipitation method and characterized using different analytical tools such as X-ray diffraction (XRD), attenuated total reflectance (ATR), and scanning electron microscope (SEM). The batch sorption investigations on 131Ba, 109Cd, 152+154Eu, and 97Zr include the influence of time, pH, and metal ion concentrations. The data reveal that S-3 has higher sorption efficiency than S-2 under all conditions. Isotherm is studied by Langmuir and Freundlich models. Binary systems data confirm that Cd(ii), Ba(ii), and Zr(iv) can be separated from Cd–Eu, Ba–Eu, and Zr–Eu binary systems using S-2 and S-3 at different pHs. Finally, the data prove that Zr(iv) and Ba(ii) can be easily separated from tertiary systems (Zr–Ba–Cd) onto S-2 and S-3 at pH 2.
{"title":"Inorganic composites based on carboxymethyl cellulose: preparation, characterization, sorption, and selectivity behavior for some radionuclides from radioactive solutions","authors":"Mohamed Ragab Abass, Maha Ali Youssef, Marwa Ahmed Eid","doi":"10.1515/ract-2023-0214","DOIUrl":"https://doi.org/10.1515/ract-2023-0214","url":null,"abstract":"This work is interested in the sorption and separation of <jats:sup>131</jats:sup>Ba, <jats:sup>109</jats:sup>Cd, <jats:sup>152+154</jats:sup>Eu, and <jats:sup>97</jats:sup>Zr from radioactive solutions onto barium molybdenum titanate loaded on carboxy methyl cellulose (BaMoTi@CMC) composites. In this work, different samples of BaMoTi@CMC composites were fabricated by the co-precipitation method and characterized using different analytical tools such as X-ray diffraction (XRD), attenuated total reflectance (ATR), and scanning electron microscope (SEM). The batch sorption investigations on <jats:sup>131</jats:sup>Ba, <jats:sup>109</jats:sup>Cd, <jats:sup>152+154</jats:sup>Eu, and <jats:sup>97</jats:sup>Zr include the influence of time, pH, and metal ion concentrations. The data reveal that S-3 has higher sorption efficiency than S-2 under all conditions. Isotherm is studied by Langmuir and Freundlich models. Binary systems data confirm that Cd(<jats:sc>ii</jats:sc>), Ba(<jats:sc>ii</jats:sc>), and Zr(<jats:sc>iv</jats:sc>) can be separated from Cd–Eu, Ba–Eu, and Zr–Eu binary systems using S-2 and S-3 at different pHs. Finally, the data prove that Zr(<jats:sc>iv</jats:sc>) and Ba(<jats:sc>ii</jats:sc>) can be easily separated from tertiary systems (Zr–Ba–Cd) onto S-2 and S-3 at pH 2.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"24 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2023-11-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529138","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}
Rhodium-103m is one of the most attractive Auger electron emitters for internal radiotherapy. The half-life of 103mRh is relatively short (56.114 min). Therefore, it needs to be produced using a generator for clinical use. Most studies of 103Pd/103mRh generators using anion-exchange resins were carried out over 50 years ago. However, these resins are no longer commercially available. In the present study, we tested a 103Pd/103mRh generator using alternative anion-exchange resins (i.e., IRA904, IRA410, SA20A, and SA11AL). No-carrier-added 103Pd was used to make the generators. The 103mRh product was eluted from the generators using 6 mL of 0.1 M HCl with a flow rate 0.5 mL/min. The generator made from SA11AL showed good performance, with a yield of 39 %, an impurity level of 103Pd in the product of 0.29 %, and an operation time of 14 min. This makes this generator competitive with previously developed ones.
铑-103m是最具吸引力的内部放射治疗俄歇电子发射体之一。103mRh的半衰期相对较短(56.114 min)。因此，需要使用发生器生产用于临床。大多数使用阴离子交换树脂的103Pd/103mRh发电机的研究是在50多年前进行的。然而，这些树脂已不再在市场上销售。在本研究中，我们使用替代阴离子交换树脂(即IRA904, IRA410, SA20A和SA11AL)测试了103Pd/103mRh发生器。发生器采用无载流子添加的103Pd。103mRh产物用6ml 0.1 M HCl以0.5 mL/min的流速从发生器中洗脱。用SA11AL制备的发生器性能良好，产率为39%，产物中杂质含量为103Pd，为0.29%，运行时间为14 min，具有较好的竞争力。
{"title":"Production of Auger-electron-emitting 103mRh via a 103Pd/103mRh generator using an anion-exchange resin","authors":"Tomoyuki Ohya, Jun Ichinose, Kotaro Nagatsu, Yumi Sugo, Noriko Ishioka, Hiroshi Watabe, Masatoshi Itoh, Katsuyuki Minegishi, Ming-Rong Zhang","doi":"10.1515/ract-2023-0238","DOIUrl":"https://doi.org/10.1515/ract-2023-0238","url":null,"abstract":"Rhodium-103m is one of the most attractive Auger electron emitters for internal radiotherapy. The half-life of <jats:sup>103m</jats:sup>Rh is relatively short (56.114 min). Therefore, it needs to be produced using a generator for clinical use. Most studies of <jats:sup>103</jats:sup>Pd/<jats:sup>103m</jats:sup>Rh generators using anion-exchange resins were carried out over 50 years ago. However, these resins are no longer commercially available. In the present study, we tested a <jats:sup>103</jats:sup>Pd/<jats:sup>103m</jats:sup>Rh generator using alternative anion-exchange resins (i.e., IRA904, IRA410, SA20A, and SA11AL). No-carrier-added <jats:sup>103</jats:sup>Pd was used to make the generators. The <jats:sup>103m</jats:sup>Rh product was eluted from the generators using 6 mL of 0.1 M HCl with a flow rate 0.5 mL/min. The generator made from SA11AL showed good performance, with a yield of 39 %, an impurity level of <jats:sup>103</jats:sup>Pd in the product of 0.29 %, and an operation time of 14 min. This makes this generator competitive with previously developed ones.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"1 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2023-11-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529149","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}
Effective treatment of uranium-containing wastewater is of great significance to the sustainable development of nuclear power and the protection of ecological environment. In this study, a highly efficient uranium adsorbent, graphene oxide (GO)/nano-hydroxyapatite (nHA) composite microspheres (nHA@rGO) was synthesized, which could effectively remove uranium from aqueous solution. Under the condition of pH = 3.5, T = 298 K, the maximum adsorption capacity reached 1672.96 mg/g. The results of batch experiments showed that the adsorption capacity of nHA@rGO microspheres was higher than that of nHA microspheres, indicating the enhancement of GO. The adsorption kinetics conformed to the pseudo second-order model. The changes of nHA@rGO microspheres before and after uranium adsorption were analyzed by FT-IR, XPS and XRD. The mechanisms of U(VI) ions adsorption onto nHA@rGO microspheres involved precipitation, surface complexation and ion exchange, in which the hydroxyl and phosphoric acid groups played important roles. The results showed that the prepared nHA@rGO microspheres can be used as an efficient and promising adsorbent for the treatment of uranium-containing wastewater.
有效处理含铀废水对核电的可持续发展和生态环境保护具有重要意义。本研究合成了一种高效的铀吸附剂——氧化石墨烯(GO)/纳米羟基磷灰石(nHA)复合微球(nHA@rGO)，可以有效地去除水溶液中的铀。在pH = 3.5, T = 298 K条件下，吸附量最大可达1672.96 mg/g。批量实验结果表明，nHA@rGO微球的吸附量高于nHA微球，表明氧化石墨烯的增强作用。吸附动力学符合准二级模型。利用FT-IR、XPS和XRD分析了nHA@rGO微球吸附铀前后的变化。nHA@rGO微球吸附U(VI)离子的机理包括沉淀、表面络合和离子交换，其中羟基和磷酸基团起重要作用。结果表明，制备的nHA@rGO微球可作为一种高效的含铀废水吸附剂。
{"title":"Efficient removal of U(VI) from aqueous solution by hydroxyapatite/graphene oxide composite microspheres","authors":"Wenjun Wu, Jianlong Wang","doi":"10.1515/ract-2023-0235","DOIUrl":"https://doi.org/10.1515/ract-2023-0235","url":null,"abstract":"Effective treatment of uranium-containing wastewater is of great significance to the sustainable development of nuclear power and the protection of ecological environment. In this study, a highly efficient uranium adsorbent, graphene oxide (GO)/nano-hydroxyapatite (nHA) composite microspheres (nHA@rGO) was synthesized, which could effectively remove uranium from aqueous solution. Under the condition of pH = 3.5, <jats:italic>T</jats:italic> = 298 K, the maximum adsorption capacity reached 1672.96 mg/g. The results of batch experiments showed that the adsorption capacity of nHA@rGO microspheres was higher than that of nHA microspheres, indicating the enhancement of GO. The adsorption kinetics conformed to the pseudo second-order model. The changes of nHA@rGO microspheres before and after uranium adsorption were analyzed by FT-IR, XPS and XRD. The mechanisms of U(VI) ions adsorption onto nHA@rGO microspheres involved precipitation, surface complexation and ion exchange, in which the hydroxyl and phosphoric acid groups played important roles. The results showed that the prepared nHA@rGO microspheres can be used as an efficient and promising adsorbent for the treatment of uranium-containing wastewater.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"33 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2023-11-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529137","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}
Satyabrata Mishra, Pankaj, Chayan Patra, Debojyoti Ghosh, N. Desigan, P. Velavendan, K. A. Venkatesan, Ananthasivan Krishnamurthy
Abstract The aqueous waste generated during the treatment of Purex lean organic phase with alkaline carbonate solution contains washable degradation products and actinides in the form of carbonate complex. Management of such aqueous waste demands quantitative removal of the main degradation product, dibutyl phosphate (HDBP) and actinides from aqueous solution. In this context, batch studies have been carried out on the separation of HDBP from aqueous solution using n-dodecane (n-DD). For this purpose, the extraction behaviour of HDBP in n-DD was studied after acidification of alkaline carbonate solution with nitric acid. The studies with simulated waste containing HDBP and U(VI) nitrate showed the loss of U(VI) as precipitate during acidification as the uranium–DBP was poorly soluble in aqueous phase. However, the loss of U(VI) decreased with increase of aqueous phase acidity showing that the adjusted acidity of the carbonate waste plays an important role in the recovery of actinides.
{"title":"Studies on the acidification of carbonate waste stream for separation of di-butyl phosphate and recovery of metal","authors":"Satyabrata Mishra, Pankaj, Chayan Patra, Debojyoti Ghosh, N. Desigan, P. Velavendan, K. A. Venkatesan, Ananthasivan Krishnamurthy","doi":"10.1515/ract-2023-0196","DOIUrl":"https://doi.org/10.1515/ract-2023-0196","url":null,"abstract":"Abstract The aqueous waste generated during the treatment of Purex lean organic phase with alkaline carbonate solution contains washable degradation products and actinides in the form of carbonate complex. Management of such aqueous waste demands quantitative removal of the main degradation product, dibutyl phosphate (HDBP) and actinides from aqueous solution. In this context, batch studies have been carried out on the separation of HDBP from aqueous solution using n-dodecane (n-DD). For this purpose, the extraction behaviour of HDBP in n-DD was studied after acidification of alkaline carbonate solution with nitric acid. The studies with simulated waste containing HDBP and U(VI) nitrate showed the loss of U(VI) as precipitate during acidification as the uranium–DBP was poorly soluble in aqueous phase. However, the loss of U(VI) decreased with increase of aqueous phase acidity showing that the adjusted acidity of the carbonate waste plays an important role in the recovery of actinides.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"41 4-5","pages":"887 - 894"},"PeriodicalIF":1.8,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139267479","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}
Lingting Xia, Han Wu, Jing Gao, Tianzhen Ye, Long Qiu, Feize Li, Tu Lan, Jijun Yang, Jiali Liao, Ning Liu, Yuanyou Yang
In this work, a gallium–nickel alloy target with a weight percentage ratio of 7:3 was successfully prepared on Cu substrate in a chloride system at room temperature. A novel organic-solvent-free separation procedure based on two columns for extracting 68Ge from irradiated Ga–Ni alloy target with high radionuclidic purity (99.99 %) was developed. By this separation procedure, the recovery of 68Ge is 95 ± 5 % and the yield of 68Ge via the nuclear reaction natGa(p,xn)68Ge was measured to be 0.27 ± 0.02 MBq/μA h.
{"title":"Efficient extraction of 68Ge from irradiated Ga–Ni alloy via a novel organic-solvent-free separation procedure","authors":"Lingting Xia, Han Wu, Jing Gao, Tianzhen Ye, Long Qiu, Feize Li, Tu Lan, Jijun Yang, Jiali Liao, Ning Liu, Yuanyou Yang","doi":"10.1515/ract-2023-0161","DOIUrl":"https://doi.org/10.1515/ract-2023-0161","url":null,"abstract":"In this work, a gallium–nickel alloy target with a weight percentage ratio of 7:3 was successfully prepared on Cu substrate in a chloride system at room temperature. A novel organic-solvent-free separation procedure based on two columns for extracting <jats:sup>68</jats:sup>Ge from irradiated Ga–Ni alloy target with high radionuclidic purity (99.99 %) was developed. By this separation procedure, the recovery of <jats:sup>68</jats:sup>Ge is 95 ± 5 % and the yield of <jats:sup>68</jats:sup>Ge via the nuclear reaction <jats:sup>nat</jats:sup>Ga(p,<jats:italic>x</jats:italic>n)<jats:sup>68</jats:sup>Ge was measured to be 0.27 ± 0.02 MBq/μA h.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"18 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2023-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"138529097","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}
Abstract This work focused the determination of the rare earth elements (REE) in Algerian bentonites named Mos and Mag using k 0 -NAA method. Eleven rare earth elements such as Ce, Nd, La, Sc, Sm, Yb, Tm, Ho, Tb, Eu and Lu were determined. Results revealed that the total light REE (LREE) in Mos (168 ppm) is higher than in Mag (68.5 ppm). In addition, the ratio of total LREE (LREE) to the total heavy rare earth elements (HREE) found to be 6.40 in Mag and 27.6 in Mos which indicates that Mos is highly rich with REE than Mag. Ce and Eu correspond to the highest and lower trace of REE in both bentonites, respectively. The concentration of Sc, Tb and Ho are comparable in two materials. All results are compared with other data of literature in terms of La, Sc, Ce, Nd, Sm and Yb. Amounts and the proportion of LREE comparing to THREE are discussed in this study.
{"title":"Determination of rare earth elements in Algerian bentonites using <i>k</i> <sub>0</sub>-NAA method","authors":"Lylia Hamidatou, Fahd Arbaoui, Radji Chahra, Hocine Slamene, Kamel Djebli, Mohamed Nadir Boucherit","doi":"10.1515/ract-2023-0210","DOIUrl":"https://doi.org/10.1515/ract-2023-0210","url":null,"abstract":"Abstract This work focused the determination of the rare earth elements (REE) in Algerian bentonites named Mos and Mag using k 0 -NAA method. Eleven rare earth elements such as Ce, Nd, La, Sc, Sm, Yb, Tm, Ho, Tb, Eu and Lu were determined. Results revealed that the total light REE (LREE) in Mos (168 ppm) is higher than in Mag (68.5 ppm). In addition, the ratio of total LREE (LREE) to the total heavy rare earth elements (HREE) found to be 6.40 in Mag and 27.6 in Mos which indicates that Mos is highly rich with REE than Mag. Ce and Eu correspond to the highest and lower trace of REE in both bentonites, respectively. The concentration of Sc, Tb and Ho are comparable in two materials. All results are compared with other data of literature in terms of La, Sc, Ce, Nd, Sm and Yb. Amounts and the proportion of LREE comparing to THREE are discussed in this study.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"55 3","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135431279","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}
Mohamed R. Abass, Sara S. Mahrous, Muhammad S. Mansy
Abstract Using batch and column procedures, the present work investigated the sorption behaviour of 137 Cs and 152+154 Eu by bentonite phosphate modified with nickel (BPN) sorbent. The kinetic data obey pseudo-1 st -order for 137 Cs and follow pseudo-2 nd -order for 152+154 Eu. Various sorption isotherm models were used to analyze equilibrium data. The thermodynamic functions reflect an endothermic and spontaneous sorption process. HCl (about 95.35 %) and CaCl 2 (about 98.13 %) showed the optimum eluents for the complete recovery of both 137 Cs and 152+154 Eu, respectively. Finally, column data show that 137 Cs and 152+154 Eu may be loaded on BNP sorbent and separated from an aqueous solution using a variety of HCl concentrations as eluent. The obtianed results revealed that BNP sorbent is suitable for recovering 137 Cs and 152+154 Eu from low-level radioactive waste effluents (LLW).
{"title":"Sorption behaviour of <sup>137</sup>Cs and <sup>152+154</sup>Eu onto bentonite phosphate modified with nickel: kinetics, isotherms, and chromatographic column application","authors":"Mohamed R. Abass, Sara S. Mahrous, Muhammad S. Mansy","doi":"10.1515/ract-2023-0168","DOIUrl":"https://doi.org/10.1515/ract-2023-0168","url":null,"abstract":"Abstract Using batch and column procedures, the present work investigated the sorption behaviour of 137 Cs and 152+154 Eu by bentonite phosphate modified with nickel (BPN) sorbent. The kinetic data obey pseudo-1 st -order for 137 Cs and follow pseudo-2 nd -order for 152+154 Eu. Various sorption isotherm models were used to analyze equilibrium data. The thermodynamic functions reflect an endothermic and spontaneous sorption process. HCl (about 95.35 %) and CaCl 2 (about 98.13 %) showed the optimum eluents for the complete recovery of both 137 Cs and 152+154 Eu, respectively. Finally, column data show that 137 Cs and 152+154 Eu may be loaded on BNP sorbent and separated from an aqueous solution using a variety of HCl concentrations as eluent. The obtianed results revealed that BNP sorbent is suitable for recovering 137 Cs and 152+154 Eu from low-level radioactive waste effluents (LLW).","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"142 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-11-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135777133","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}
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