The present paper describes a simple method for the determination of uranium in uranium process stream solutions by reversed-phase liquid chromatographic method using C18 column, mixture of α-hydroxy isobutyric acid and methanol as eluent and flow-through spectrophotometer detector. This method has an advantage that interfering elements like rare-earth elements do not retain on the column and elute near the solvent peak thereby not interfering with uranium elution peak. Different eluents and parameters like pH, concentration of eluent are studied for the purpose. The spiking standard recovery was found to be more than 90 %. The developed method has been compared with other techniques and found to be in agreement.
{"title":"Reverse phase liquid chromatographic method for the measurement of uranium in process stream solutions from uranium extraction facility","authors":"Yarasi Balaji Rao, Shehanaz Bano, Putta V. Nagendra Kumar, Dinesh Srivastava","doi":"10.1515/ract-2023-0187","DOIUrl":"https://doi.org/10.1515/ract-2023-0187","url":null,"abstract":"The present paper describes a simple method for the determination of uranium in uranium process stream solutions by reversed-phase liquid chromatographic method using C18 column, mixture of α-hydroxy isobutyric acid and methanol as eluent and flow-through spectrophotometer detector. This method has an advantage that interfering elements like rare-earth elements do not retain on the column and elute near the solvent peak thereby not interfering with uranium elution peak. Different eluents and parameters like pH, concentration of eluent are studied for the purpose. The spiking standard recovery was found to be more than 90 %. The developed method has been compared with other techniques and found to be in agreement.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"205 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759248","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}
Yarasi Balaji Rao, Sirivella N. V. M. S. Gupta, Putta V. Nagendra Kumar, Dinesh Srivastava
The present paper discusses about the method developed for complete chemical characterization of Zirconium Washed and Dried Frit (WDF) and Reactor Grade ZrO2 powder which includes nonmetallic element sulphur using Inductively Coupled Plasma Optical Emission Spectrometer (ICP-OES). Studies have been carried-out on several important aspects of method development such as effect of matrix on determination of analytes, removal of matrix using different solvents, selection of interference free & sensitive wavelengths, calibration strategies like internal standard & standard addition, optimization of several instrumental parameters which includes RF power, plasma gas flow, nebulizer gas flow, nitrogen purging etc., and are discussed. A % RSD of less than 1 % for Zr and up to 3 % for other elements has been achieved in this method. The developed method has been validated using standard recovery of spiked real time samples with known amount of reference materials. Integrated approach adopted in the development of this method has resulted in reduction of analytical waste generated and also enabled to give quick analytical feedback to production plant for downstream processing.
{"title":"Zirconium sponge production: an integrated approach for chemical characterization of process intermediates using ICP-OES","authors":"Yarasi Balaji Rao, Sirivella N. V. M. S. Gupta, Putta V. Nagendra Kumar, Dinesh Srivastava","doi":"10.1515/ract-2023-0231","DOIUrl":"https://doi.org/10.1515/ract-2023-0231","url":null,"abstract":"The present paper discusses about the method developed for complete chemical characterization of Zirconium Washed and Dried Frit (WDF) and Reactor Grade ZrO<jats:sub>2</jats:sub> powder which includes nonmetallic element sulphur using Inductively Coupled Plasma Optical Emission Spectrometer (ICP-OES). Studies have been carried-out on several important aspects of method development such as effect of matrix on determination of analytes, removal of matrix using different solvents, selection of interference free & sensitive wavelengths, calibration strategies like internal standard & standard addition, optimization of several instrumental parameters which includes RF power, plasma gas flow, nebulizer gas flow, nitrogen purging etc., and are discussed. A % RSD of less than 1 % for Zr and up to 3 % for other elements has been achieved in this method. The developed method has been validated using standard recovery of spiked real time samples with known amount of reference materials. Integrated approach adopted in the development of this method has resulted in reduction of analytical waste generated and also enabled to give quick analytical feedback to production plant for downstream processing.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"120 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759125","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}
Metal fuels are considered as the promising candidates for future fast breeder reactors. Pyro-chemical reprocessing is the ideal method for reprocessing spent metallic fuels due to the inherent process advantages. Electrorefining run was demonstrated in a hot cell facility with irradiated U-6 wt% Zr alloy at 500 °C using LiCl–KCl eutectic melt. In order to understand the behavior of the actinides and various fission products during high-temperature electrolysis, various process streams, viz., irradiated metal alloy fuel, the eutectic salt, and the cathode deposit were analyzed for the uranium, plutonium, and other fission product contents. Various methods employed for characterizing the process streams and the behaviors of some of the fission products during the electrolysis process are highlighted. The major gamma emitting radionuclides present in the irradiated fuel were 106Ru, 125Sb, 134Cs, 137Cs, 144Ce, and 154Eu. During electrorefining, cesium, cerium and europium were oxidized and dissolved in the molten media, whereas ruthenium and antimony remained in the anode basket. A minor contamination of zirconium was found in the cathode deposit.
{"title":"Radiochemical and chemical characterization of fuel, salt, and deposit from the electrorefining of irradiated U-6 wt% Zr in hot cells","authors":"Dwarapudi Bola Sankar, Rajeswari Seshadri, Kalaiyarasu Thirunavukkarasu, Gurudas Pakhui, Jakkula Siva Brahmaji Rao, Suranjan Bera, Balija Sreenivasulu, Kumaresan Radhakrishnan, Periasamy Manoravi, Venkataraman Jayaraman","doi":"10.1515/ract-2023-0203","DOIUrl":"https://doi.org/10.1515/ract-2023-0203","url":null,"abstract":"Metal fuels are considered as the promising candidates for future fast breeder reactors. Pyro-chemical reprocessing is the ideal method for reprocessing spent metallic fuels due to the inherent process advantages. Electrorefining run was demonstrated in a hot cell facility with irradiated U-6 wt% Zr alloy at 500 °C using LiCl–KCl eutectic melt. In order to understand the behavior of the actinides and various fission products during high-temperature electrolysis, various process streams, viz., irradiated metal alloy fuel, the eutectic salt, and the cathode deposit were analyzed for the uranium, plutonium, and other fission product contents. Various methods employed for characterizing the process streams and the behaviors of some of the fission products during the electrolysis process are highlighted. The major gamma emitting radionuclides present in the irradiated fuel were <jats:sup>106</jats:sup>Ru, <jats:sup>125</jats:sup>Sb, <jats:sup>134</jats:sup>Cs, <jats:sup>137</jats:sup>Cs, <jats:sup>144</jats:sup>Ce, and <jats:sup>154</jats:sup>Eu. During electrorefining, cesium, cerium and europium were oxidized and dissolved in the molten media, whereas ruthenium and antimony remained in the anode basket. A minor contamination of zirconium was found in the cathode deposit.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"68 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139772984","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}
Synthesis of PSMA-617, a peptide based ligand used in the preparation of nuclear medicine, 177Lu-PSMA-617, for the treatment of prostate cancer, is demonstrated in 6 steps, starting from appropriately protected amino acid building blocks. A solution phase Boc-strategy was adopted for the synthesis of peptide, wherein deprotection of carbamate group using HCl (g), was employed as the key step. The synthesis furnished PSMA-617 in purity >99.5 % as confirmed by HPLC analysis. ESI-MS and NMR analysis supported the structural integrity of the compound. The synthesized ligand was radiolabelled using 177Lu to generate the desired radiopharmaceutical, 177Lu-PSMA-617, in radiochemical purity >98 %, as revealed by radio HPLC and TLC analysis. This establishes its potential as a nuclear medicine for therapeutic application.
{"title":"Total chemical synthesis of PSMA-617: an API for prostate cancer endotherapeutic applications","authors":"Kalangattu Sundaran Ajish Kumar, Anupam Mathur","doi":"10.1515/ract-2023-0205","DOIUrl":"https://doi.org/10.1515/ract-2023-0205","url":null,"abstract":"Synthesis of PSMA-617, a peptide based ligand used in the preparation of nuclear medicine, <jats:sup>177</jats:sup>Lu-PSMA-617, for the treatment of prostate cancer, is demonstrated in 6 steps, starting from appropriately protected amino acid building blocks. A solution phase Boc-strategy was adopted for the synthesis of peptide, wherein deprotection of carbamate group using HCl (g), was employed as the key step. The synthesis furnished PSMA-617 in purity >99.5 % as confirmed by HPLC analysis. ESI-MS and NMR analysis supported the structural integrity of the compound. The synthesized ligand was radiolabelled using <jats:sup>177</jats:sup>Lu to generate the desired radiopharmaceutical, <jats:sup>177</jats:sup>Lu-PSMA-617, in radiochemical purity >98 %, as revealed by radio HPLC and TLC analysis. This establishes its potential as a nuclear medicine for therapeutic application.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"174 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759123","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}
97Ru is a key radionuclide sought for diagnostic imaging due to its low-energy and intense γ-rays of 215.7 keV and 324.5 keV. New reaction routes to produce this radionuclide are constantly being investigated. A crucial step in carrying out such reactions is a reliable beforehand estimate of the production cross section of radionuclide and optimization conditions through robust theoretical frameworks. Existing literature on α + 95Mo reaction has been freshly examined to understand the excitation function of 97Ru. The data have been compared to other reactions of different projectiles on medium-mass targets. The reaction codes pace4, empire-3.2.2, and talys-1.96 have been employed to decipher the reaction mechanism and check the predictive ability of underlying theoretical models. The yield of 97Ru at different projectile energies and thick target yield in the optimum energy range has also been determined from the theoretical modeling.
{"title":"Theoretical analysis of light and heavy-ion induced reactions: production of medically relevant 97Ru","authors":"Malvika Sagwal, Moumita Maiti","doi":"10.1515/ract-2023-0199","DOIUrl":"https://doi.org/10.1515/ract-2023-0199","url":null,"abstract":"<jats:sup>97</jats:sup>Ru is a key radionuclide sought for diagnostic imaging due to its low-energy and intense γ-rays of 215.7 keV and 324.5 keV. New reaction routes to produce this radionuclide are constantly being investigated. A crucial step in carrying out such reactions is a reliable beforehand estimate of the production cross section of radionuclide and optimization conditions through robust theoretical frameworks. Existing literature on <jats:italic>α</jats:italic> + <jats:sup>95</jats:sup>Mo reaction has been freshly examined to understand the excitation function of <jats:sup>97</jats:sup>Ru. The data have been compared to other reactions of different projectiles on medium-mass targets. The reaction codes <jats:sc>pace</jats:sc>4, <jats:sc>empire</jats:sc>-3.2.2, and <jats:sc>talys</jats:sc>-1.96 have been employed to decipher the reaction mechanism and check the predictive ability of underlying theoretical models. The yield of <jats:sup>97</jats:sup>Ru at different projectile energies and thick target yield in the optimum energy range has also been determined from the theoretical modeling.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"16 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759121","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}
Mahesh Choudhary, Namrata Singh, Aman Sharma, Aman Gandhi, Mahima Upadhyay, Rebecca Pachuau, Sandipan Dasgupta, Jagannath Datta, Ajay Kumar
Excitation functions of alpha-particle induced nuclear reactions on natSn have been presented in the 11–40 MeV energy range. In the present study, the stacked-foil activation technique followed by offline gamma-ray spectrometry was used to measure the production of 119Te, 121Te, 122Sb and 126Sb from alpha-particle induced reactions on natSn. The TALYS nuclear code was used to calculate the theoretical predictions of the excitation functions of natSn(α,x) nuclear reactions. The measured data of the above-mentioned nuclear reactions were compared with the theoretical predictions and the experimental results available from EXFOR. In this study, covariance analysis was performed to calculate the uncertainty propagation in the measured cross sections.
{"title":"Excitation functions of alpha-particle induced nuclear reactions on nat Sn","authors":"Mahesh Choudhary, Namrata Singh, Aman Sharma, Aman Gandhi, Mahima Upadhyay, Rebecca Pachuau, Sandipan Dasgupta, Jagannath Datta, Ajay Kumar","doi":"10.1515/ract-2023-0202","DOIUrl":"https://doi.org/10.1515/ract-2023-0202","url":null,"abstract":"Excitation functions of alpha-particle induced nuclear reactions on <jats:sup> <jats:italic>nat</jats:italic> </jats:sup>Sn have been presented in the 11–40 MeV energy range. In the present study, the stacked-foil activation technique followed by offline gamma-ray spectrometry was used to measure the production of <jats:sup>119</jats:sup>Te, <jats:sup>121</jats:sup>Te, <jats:sup>122</jats:sup>Sb and <jats:sup>126</jats:sup>Sb from alpha-particle induced reactions on <jats:sup> <jats:italic>nat</jats:italic> </jats:sup>Sn. The TALYS nuclear code was used to calculate the theoretical predictions of the excitation functions of <jats:sup> <jats:italic>nat</jats:italic> </jats:sup>Sn(<jats:italic>α</jats:italic>,x) nuclear reactions. The measured data of the above-mentioned nuclear reactions were compared with the theoretical predictions and the experimental results available from EXFOR. In this study, covariance analysis was performed to calculate the uncertainty propagation in the measured cross sections.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"16 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759126","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}
Sourav Patra, Sachin Jadhav, Priyalata Shetty, Khajan Singh, Ardhi Rajeswari, K. V. Vimalnath, Avik Chakraborty, Rubel Chakravarty, Sudipta Chakraborty
Glomerular filtration rate (GFR) could be determined more accurately using renal positron emission tomography (PET) than conventional gamma imaging. Copper-64 [T½ = 12.7 h, Eβ+ (max) = 653 keV, β+ branching ratio = 17.8 %, 1346 keV γ-photon (0.54 %), EC (43.8 %), β− emission (38.4 %)] in the form of its hydrophilic complex with 1,4,7-triazacyclononane-1,4,7-triacetic acid (NOTA) is proposed as a potent formulation for renal PET imaging. A lyophilized kit was developed for formulation of ∼370 MBq dose of [64Cu]Cu–NOTA complex in a facile single step process using 64Cu produced by thermal neutron activation in a research reactor. The complex could be synthesized with >99 % yield and retained its integrity even when challenged by apoferritin. The rapid accumulation of [64Cu]Cu–NOTA in the kidney and clearance through urinary path was demonstrated using PET/CT imaging and ex vivo biodistribution study carried out in healthy Wistar rats to elucidate its effectiveness as a renal PET-imaging agent.
{"title":"Preparation of [64Cu]Cu–NOTA complex as a potential renal PET imaging agent using 64Cu produced via the direct activation route","authors":"Sourav Patra, Sachin Jadhav, Priyalata Shetty, Khajan Singh, Ardhi Rajeswari, K. V. Vimalnath, Avik Chakraborty, Rubel Chakravarty, Sudipta Chakraborty","doi":"10.1515/ract-2023-0206","DOIUrl":"https://doi.org/10.1515/ract-2023-0206","url":null,"abstract":"Glomerular filtration rate (GFR) could be determined more accurately using renal positron emission tomography (PET) than conventional gamma imaging. Copper-64 [<jats:italic>T</jats:italic> <jats:sub>½</jats:sub> = 12.7 h, <jats:italic>E</jats:italic> <jats:sub>β+</jats:sub> (max) = 653 keV, β<jats:sup>+</jats:sup> branching ratio = 17.8 %, 1346 keV γ-photon (0.54 %), EC (43.8 %), β<jats:sup>−</jats:sup> emission (38.4 %)] in the form of its hydrophilic complex with 1,4,7-triazacyclononane-1,4,7-triacetic acid (NOTA) is proposed as a potent formulation for renal PET imaging. A lyophilized kit was developed for formulation of ∼370 MBq dose of [<jats:sup>64</jats:sup>Cu]Cu–NOTA complex in a facile single step process using <jats:sup>64</jats:sup>Cu produced by thermal neutron activation in a research reactor. The complex could be synthesized with >99 % yield and retained its integrity even when challenged by apoferritin. The rapid accumulation of [<jats:sup>64</jats:sup>Cu]Cu–NOTA in the kidney and clearance through urinary path was demonstrated using PET/CT imaging and <jats:italic>ex vivo</jats:italic> biodistribution study carried out in healthy Wistar rats to elucidate its effectiveness as a renal PET-imaging agent.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"16 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759219","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}
Jayaprakasam Selvakumar, Kumari Anshul, Padala A. Nishad, Bhaskarapillai Anupkumar, Subramanian Srinivasan, Nethapakkam R. Jawahar, Appadurai L. Rufus, Jayantha K. Gayen, Tulasi V. Krishna Mohan
Cerium hydroxide, Ce(OH)4 (Ce), has been synthesised and assessed as a Ru-selective adsorbent for treating alkaline radioactive liquid waste. Infrared spectroscopy, thermal analysis, scanning electron microscopy, and energy-dispersive X-ray spectroscopy investigations confirmed the successful formation of nanocrystalline Ce from Ce(NO3)3·6H2O. Selective removal of 106Ru from the ion-exchange effluent of intermediate-level liquid waste (ILW) by Ce was assessed using a high-pure germanium (HPGe) gamma-ray spectrometer. The calculated average distribution coefficient (kD) was ∼200 mL/g. The percentage removal of 106Ru using Ce by varying time, [106Ru] and [Ce] was calculated. The adsorption of 106Ru on Ce follows pseudo-second-order and Freundlich isotherms. The calculated Qmax was 93,584 Bq/g. Accelerated leaching studies of the Ru-laden Ce cement product were carried out and found suitable for transport and disposal. Further, Ce-Polyether sulphone (Ce-PES) and Ce-Chitosan (CeC) composites were prepared and assessed for their Ru-uptake capacity for engineering scale application.
氢氧化铈（Ce(OH)4 (Ce)）已被合成并评估为一种处理碱性放射性液体废物的 Ru 选择性吸附剂。红外光谱、热分析、扫描电子显微镜和能量色散 X 射线光谱研究证实，Ce(NO3)3-6H2O 成功地形成了纳米晶 Ce。使用高纯锗（HPGe）伽马射线光谱仪评估了 Ce 从中级液体废物（ILW）离子交换流出物中选择性去除 106Ru 的情况。计算得出的平均分布系数（k D）为 200 mL/g。通过改变时间、[106Ru]和[Ce]，计算了利用 Ce 去除 106Ru 的百分比。106Ru 在 Ce 上的吸附遵循伪二阶和 Freundlich 等温线。计算得出的最大 Q 值为 93,584 Bq/g。对含有 Ru 的 Ce 水泥产品进行了加速沥滤研究，发现其适合运输和处置。此外，还制备了 Ce 聚醚砜（Ce-PES）和 Ce 壳聚糖（CeC）复合材料，并对其在工程规模应用中的 Ru 吸收能力进行了评估。
{"title":"Nanocrystalline Ce(OH)4-based materials: ruthenium selective adsorbent for highly alkaline radioactive liquid waste","authors":"Jayaprakasam Selvakumar, Kumari Anshul, Padala A. Nishad, Bhaskarapillai Anupkumar, Subramanian Srinivasan, Nethapakkam R. Jawahar, Appadurai L. Rufus, Jayantha K. Gayen, Tulasi V. Krishna Mohan","doi":"10.1515/ract-2023-0194","DOIUrl":"https://doi.org/10.1515/ract-2023-0194","url":null,"abstract":"Cerium hydroxide, Ce(OH)<jats:sub>4</jats:sub> (Ce), has been synthesised and assessed as a Ru-selective adsorbent for treating alkaline radioactive liquid waste. Infrared spectroscopy, thermal analysis, scanning electron microscopy, and energy-dispersive X-ray spectroscopy investigations confirmed the successful formation of nanocrystalline Ce from Ce(NO<jats:sub>3</jats:sub>)<jats:sub>3</jats:sub>·6H<jats:sub>2</jats:sub>O. Selective removal of <jats:sup>106</jats:sup>Ru from the ion-exchange effluent of intermediate-level liquid waste (ILW) by Ce was assessed using a high-pure germanium (HPGe) gamma-ray spectrometer. The calculated average distribution coefficient (<jats:italic>k</jats:italic> <jats:sub>D</jats:sub>) was ∼200 mL/g. The percentage removal of <jats:sup>106</jats:sup>Ru using Ce by varying time, [<jats:sup>106</jats:sup>Ru] and [Ce] was calculated. The adsorption of <jats:sup>106</jats:sup>Ru on Ce follows pseudo-second-order and Freundlich isotherms. The calculated <jats:italic>Q</jats:italic> <jats:sub>max</jats:sub> was 93,584 Bq/g. Accelerated leaching studies of the Ru-laden Ce cement product were carried out and found suitable for transport and disposal. Further, Ce-Polyether sulphone (Ce-PES) and Ce-Chitosan (CeC) composites were prepared and assessed for their Ru-uptake capacity for engineering scale application.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"18 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759247","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}
Alexandra Becker, Holger Lippold, Jantje Pauline Bäcker, Detlev Belder, Cornelius Fischer
The handling and analysis of gaseous tritium is of interest for hydrogen isotope separation experiments. In this work, we present an easy-to-handle setup for catalytic oxidation to HTO, recovering all of the initially dosed gaseous tritium as determined by LSC, using CuO as a catalyst at a reaction temperature of 900 °C. Aiming to reduce cocktail waste, the LSC determination was downscaled to a microfluidic setup. The performance was evaluated based on the counting efficiency, which was shown to decrease significantly, as the sample volume was reduced to µl amounts, while no changes were observed over a wide range of sample-to-cocktail ratios.
{"title":"An LSC approach for tritium determination in gaseous mixtures optimized with respect to handling, reaction parameters and miniaturization towards microfluidic analysis","authors":"Alexandra Becker, Holger Lippold, Jantje Pauline Bäcker, Detlev Belder, Cornelius Fischer","doi":"10.1515/ract-2023-0262","DOIUrl":"https://doi.org/10.1515/ract-2023-0262","url":null,"abstract":"The handling and analysis of gaseous tritium is of interest for hydrogen isotope separation experiments. In this work, we present an easy-to-handle setup for catalytic oxidation to HTO, recovering all of the initially dosed gaseous tritium as determined by LSC, using CuO as a catalyst at a reaction temperature of 900 °C. Aiming to reduce cocktail waste, the LSC determination was downscaled to a microfluidic setup. The performance was evaluated based on the counting efficiency, which was shown to decrease significantly, as the sample volume was reduced to µl amounts, while no changes were observed over a wide range of sample-to-cocktail ratios.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"13 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759119","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 Fares, Mohammed Messaoudi, Mohamed Yacine Debili, Kassida Negara
Detecting nuclear radiation presents a distinctive challenge, particularly with neutrons, which are neutral particles. The method of direct detection involves the utilization of a converter material, acting as an intermediary. Boron plays a pivotal role in this process, reacting with thermal neutrons to generate alpha particles and lithium, with a notable energy release of 2.314 MeV during the 10B (n,α) 7Li reaction. This facilitates effective identification and measurement of neutrons in radiation detection systems. The paths of the particles α (for E = 1.474 MeV) and Li (for ELi = 0.842 MeV). The active medium of the nuclear detector, typically a gas, undergoes ionization by these highly charged particles, or they form ion pairs that are subsequently collected by electrodes to produce the signal at the detector’s output. Various deposit methods can be used for this purpose, electrophoresis offers a distinct advantage in terms of both simplicity and precision. This study details the utilization of the electrophoresis technique for the deposition of boron on the tube walls of prototype detectors developed within our laboratory.
{"title":"Application of thin boron deposit by electrophoresis as neutron detectors","authors":"Mohamed Fares, Mohammed Messaoudi, Mohamed Yacine Debili, Kassida Negara","doi":"10.1515/ract-2023-0226","DOIUrl":"https://doi.org/10.1515/ract-2023-0226","url":null,"abstract":"Detecting nuclear radiation presents a distinctive challenge, particularly with neutrons, which are neutral particles. The method of direct detection involves the utilization of a converter material, acting as an intermediary. Boron plays a pivotal role in this process, reacting with thermal neutrons to generate alpha particles and lithium, with a notable energy release of 2.314 MeV during the <jats:sup>10</jats:sup>B (n,α) <jats:sup>7</jats:sup>Li reaction. This facilitates effective identification and measurement of neutrons in radiation detection systems. The paths of the particles α (for <jats:italic>E</jats:italic> = 1.474 MeV) and Li (for <jats:italic>E</jats:italic> <jats:sub>Li</jats:sub> = 0.842 MeV). The active medium of the nuclear detector, typically a gas, undergoes ionization by these highly charged particles, or they form ion pairs that are subsequently collected by electrodes to produce the signal at the detector’s output. Various deposit methods can be used for this purpose, electrophoresis offers a distinct advantage in terms of both simplicity and precision. This study details the utilization of the electrophoresis technique for the deposition of boron on the tube walls of prototype detectors developed within our laboratory.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":"30 1","pages":""},"PeriodicalIF":1.8,"publicationDate":"2024-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139772817","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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