Meghnath Sen, Rakesh Shukla, Raman K. Mishra, Nimai Pathak, Vilippalil Sathian, Probal Chaudhury
The manuscript reports the synthesis of Dy3+ incorporated lithium magnesium borate glass by melt quenching technique. FTIR study revealed the presence of both BO3 as well as tetrahedral BO4 units through their characteristic frequencies. Photoluminescence (PL) study of unirradiated samples confirmed the presence of Dy dopant in the ‘+3’ oxidation states from the characteristic emissions at 482, 578, 666 and 716 nm corresponding to 4F9/2 → 6H15/2, 4F9/2 → 6H13/2 and 4F9/2 → 6H11/2, 4F9/2 → 6H9/2 transitions, respectively. Thermal neutron and gamma irradiated PL emission and lifetime characteristics were discussed in details based on the different defect centers. Thermal neutron irradiated TL study showed that the material has a broad and single dosimetry glow peak at about 450 K which showed high fading due to low temperature peak. TL based neutron sensitivity of LMB: Dy3+ was found to be about 37.4 times less than that of standard TLD-100 (LiF: Mg, Ti) powder. The net TL response from about 3 to 83 mSv of neutron dose was found to be linear (Adj. R2 = 0.9994) which is one of the most desirable properties for dosimetry applications. In addition, the TL trap parameters were evaluated using both deconvolution of TL glow curve and peak shape method as suggested by Chen which were found to be matching with each other.
{"title":"Development of Dy3+ doped lithium magnesium borate glass system for thermoluminescence based neutron dosimetry applications","authors":"Meghnath Sen, Rakesh Shukla, Raman K. Mishra, Nimai Pathak, Vilippalil Sathian, Probal Chaudhury","doi":"10.1515/ract-2023-0209","DOIUrl":"https://doi.org/10.1515/ract-2023-0209","url":null,"abstract":"The manuscript reports the synthesis of Dy<jats:sup>3+</jats:sup> incorporated lithium magnesium borate glass by melt quenching technique. FTIR study revealed the presence of both BO<jats:sub>3</jats:sub> as well as tetrahedral BO<jats:sub>4</jats:sub> units through their characteristic frequencies. Photoluminescence (PL) study of unirradiated samples confirmed the presence of Dy dopant in the ‘+3’ oxidation states from the characteristic emissions at 482, 578, 666 and 716 nm corresponding to <jats:sup>4</jats:sup>F<jats:sub>9/2</jats:sub> → <jats:sup>6</jats:sup>H<jats:sub>15/2</jats:sub>, <jats:sup>4</jats:sup>F<jats:sub>9/2</jats:sub> → <jats:sup>6</jats:sup>H<jats:sub>13/2</jats:sub> and <jats:sup>4</jats:sup>F<jats:sub>9/2</jats:sub> → <jats:sup>6</jats:sup>H<jats:sub>11/2</jats:sub>, <jats:sup>4</jats:sup>F<jats:sub>9/2</jats:sub> → <jats:sup>6</jats:sup>H<jats:sub>9/2</jats:sub> transitions, respectively. Thermal neutron and gamma irradiated PL emission and lifetime characteristics were discussed in details based on the different defect centers. Thermal neutron irradiated TL study showed that the material has a broad and single dosimetry glow peak at about 450 K which showed high fading due to low temperature peak. TL based neutron sensitivity of LMB: Dy<jats:sup>3+</jats:sup> was found to be about 37.4 times less than that of standard TLD-100 (LiF: Mg, Ti) powder. The net TL response from about 3 to 83 mSv of neutron dose was found to be linear (Adj. R<jats:sup>2</jats:sup> = 0.9994) which is one of the most desirable properties for dosimetry applications. In addition, the TL trap parameters were evaluated using both deconvolution of TL glow curve and peak shape method as suggested by Chen which were found to be matching with each other.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-03-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140108296","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}
In this study, preclinical evaluation and dosimetric estimation of [64Cu]Cu-BPAMD, as a new bone-seeking agent for PET imaging, was studied. [64Cu]Cu-BPAMD was produced with a specific activity of 8.7 GBq/µmol and radiochemical purity (R.P.) of >98 %. The HA binding results showed the binding of nearly all [64Cu]Cu-BPAMD complex to HA at about 15 mg. Biodistribution studies in the male Syrian rats indicated considerable accumulation in the bone with negligible uptake in the other organs. The bone surface and the bone marrow receiving 0.199 and 0.092 mGy/MBq, respectively, are the organs with the most absorbed dose. This study confirms the production of [64Cu]Cu-BPAMD with high R.P. showing high potential for PET-imaging of bone metastases. The lower absorbed dose of mainly human organs compared to 68Ga-BPAMD can be considered one of the advantages of this new radiolabeled compound.
本研究对[64Cu]Cu-BPAMD（一种用于 PET 成像的新型骨探寻剂）进行了临床前评估和剂量估算。所制备的[64Cu]Cu-BPAMD 的比活度为 8.7 GBq/µmol，放射化学纯度（R.P.）为 98%。HA 结合结果显示，几乎所有的 [64Cu]Cu-BPAMD 复合物都与 HA 结合，结合量约为 15 毫克。在雄性叙利亚大鼠体内进行的生物分布研究表明，[64Cu]Cu-BPAMD 复合物在骨骼中大量蓄积，而在其他器官中的吸收则微乎其微。骨表面和骨髓分别吸收了 0.199 和 0.092 mGy/MBq，是吸收剂量最大的器官。这项研究证实了[64Cu]Cu-BPAMD 的生产具有较高的 R.P.，在骨转移的 PET 成像方面具有很大的潜力。与 68Ga-BPAMD 相比，主要人体器官的吸收剂量更低，这可以说是这种新型放射性标记化合物的优势之一。
{"title":"Development of [64Cu]Cu-BPAMD for PET imaging of bone metastases","authors":"Samaneh Zolghadri, Fateme Badipa, Hassan Yousefnia, Zahra Shiri-Yekta","doi":"10.1515/ract-2023-0236","DOIUrl":"https://doi.org/10.1515/ract-2023-0236","url":null,"abstract":"In this study, preclinical evaluation and dosimetric estimation of [<jats:sup>64</jats:sup>Cu]Cu-BPAMD, as a new bone-seeking agent for PET imaging, was studied. [<jats:sup>64</jats:sup>Cu]Cu-BPAMD was produced with a specific activity of 8.7 GBq/µmol and radiochemical purity (R.P.) of >98 %. The HA binding results showed the binding of nearly all [<jats:sup>64</jats:sup>Cu]Cu-BPAMD complex to HA at about 15 mg. Biodistribution studies in the male Syrian rats indicated considerable accumulation in the bone with negligible uptake in the other organs. The bone surface and the bone marrow receiving 0.199 and 0.092 mGy/MBq, respectively, are the organs with the most absorbed dose. This study confirms the production of [<jats:sup>64</jats:sup>Cu]Cu-BPAMD with high R.P. showing high potential for PET-imaging of bone metastases. The lower absorbed dose of mainly human organs compared to <jats:sup>68</jats:sup>Ga-BPAMD can be considered one of the advantages of this new radiolabeled compound.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140054638","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}
In this experimental work, guar gum powder was exposed to gamma radiation from a 60Co source at absorbed doses of 0, 10, 30, 50, 80, 100, 150 kGy at dose rate of 1.62 Gy/s. Raman spectroscopy was applied to measure the intensity of the samples ranging from of 500–4600 cm−1. The intensity versus Raman shift was evaluated at 3800–4000 cm−1. Then the curve was fitted linearly. The slope of the lines was determined in each absorbed dose. Results indicated that the absolute values of the slope of each line were enhanced with increasing the absorbed dose. This trend was linear within the absorbed dose ranging from of 0–50 kGy, in which was saturated after 80 kGy. Results showed that guar gum can be applied as a passive dosimeter at radiation processing level.
{"title":"Investigation of the dose-response linearity of guar gum for gamma-ray dosimetry at radiation processing levels using Raman spectroscopy","authors":"Shahryar Malekie, Amir Veiskarami","doi":"10.1515/ract-2023-0246","DOIUrl":"https://doi.org/10.1515/ract-2023-0246","url":null,"abstract":"In this experimental work, guar gum powder was exposed to gamma radiation from a <jats:sup>60</jats:sup>Co source at absorbed doses of 0, 10, 30, 50, 80, 100, 150 kGy at dose rate of 1.62 Gy/s. Raman spectroscopy was applied to measure the intensity of the samples ranging from of 500–4600 cm<jats:sup>−1</jats:sup>. The intensity versus Raman shift was evaluated at 3800–4000 cm<jats:sup>−1</jats:sup>. Then the curve was fitted linearly. The slope of the lines was determined in each absorbed dose. Results indicated that the absolute values of the slope of each line were enhanced with increasing the absorbed dose. This trend was linear within the absorbed dose ranging from of 0–50 kGy, in which was saturated after 80 kGy. Results showed that guar gum can be applied as a passive dosimeter at radiation processing level.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-02-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139956325","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}
Yousef Fazaeli, Gholamreza Shahhoseini, Alireza Neisi, James Jacob Sasanya, Parviz Ashtari, Shahzad Feizi
Antimicrobial resistance (AMR) as one of the world’s most pressing public health problems needs immediate attention, because it has the ability to affect the human healthcare, agriculture, and veterinary industries. Despite warnings about overuse and their implications, antimicrobials are overprescribed worldwide for humans and animals, which leads to the promotion of resistant microorganisms such as bacteria. Food is a medium for exposure to or transfer of residues of the drugs and can contribute to the burden of the pharmaceuticals associated with development of AMR. Studying on residues of veterinary drugs in foods is essential in the fight against AMR. Herein, we introduce a new method for visualizing the residues of a veterinary drug in animal matrices using radionuclides, called “Depletion Imaging”. Amoxicillin was chosen to be the first antimicrobial for this study. The drug was labeled with [62Zn/65Zn] ZnCl2. Radiolabelled amoxicillin and non-labeled amoxicillin were administrated to rainbow trout fish simultaneously. To enable visualization of the remaining residues of amoxicillin in fish, In-vivo positron emission tomography (PET) imaging was done at different intervals from 30 min to 21 days after administration. Evaluation of the amount of radiolabelled amoxicillin in fish was done using a high purity germanium (HPGe) nuclear detector, and enzyme linked immunosorbent assay (ELISA) technique was used for the non-labeled drug. In this study, a comprehensive method for in-house production of zinc radioisotopes was also included. The results showed that depletion imaging and biodistribution study based on gamma spectroscopy of radionuclides in tissues, is a precise method for accurate understanding of the drug’s distribution, metabolic and excretory profile.
抗菌药耐药性（AMR）是全球最紧迫的公共卫生问题之一，需要立即引起重视，因为它有可能影响人类医疗保健、农业和兽医行业。尽管有关于过度使用抗菌药及其影响的警告，但全世界仍在为人类和动物过度使用抗菌药，从而导致细菌等抗药性微生物的滋生。食品是接触或转移药物残留的媒介，可加重与 AMR 发展相关的药物负担。研究食品中的兽药残留对抗击 AMR 至关重要。在此，我们介绍一种利用放射性核素观察动物基质中兽药残留的新方法，称为 "损耗成像"。阿莫西林被选为本研究的第一种抗菌素。该药物用 [62Zn/65Zn] ZnCl2 标记。同时给虹鳟鱼注射放射性标记的阿莫西林和未标记的阿莫西林。为了观察阿莫西林在鱼体内的残留情况，在用药后 30 分钟至 21 天的不同时间间隔进行了体内正电子发射断层扫描（PET）成像。使用高纯锗（HPGe）核检测器评估鱼体内放射性标记阿莫西林的含量，使用酶联免疫吸附试验（ELISA）技术检测非标记药物。这项研究还包括一种内部生产锌放射性同位素的综合方法。研究结果表明，基于组织中放射性核素伽马能谱的耗竭成像和生物分布研究是准确了解药物分布、代谢和排泄情况的精确方法。
{"title":"A novel method for evaluating the depletion of veterinary pharmaceuticals using radioisotopes","authors":"Yousef Fazaeli, Gholamreza Shahhoseini, Alireza Neisi, James Jacob Sasanya, Parviz Ashtari, Shahzad Feizi","doi":"10.1515/ract-2023-0249","DOIUrl":"https://doi.org/10.1515/ract-2023-0249","url":null,"abstract":"Antimicrobial resistance (AMR) as one of the world’s most pressing public health problems needs immediate attention, because it has the ability to affect the human healthcare, agriculture, and veterinary industries. Despite warnings about overuse and their implications, antimicrobials are overprescribed worldwide for humans and animals, which leads to the promotion of resistant microorganisms such as bacteria. Food is a medium for exposure to or transfer of residues of the drugs and can contribute to the burden of the pharmaceuticals associated with development of AMR. Studying on residues of veterinary drugs in foods is essential in the fight against AMR. Herein, we introduce a new method for visualizing the residues of a veterinary drug in animal matrices using radionuclides, called “Depletion Imaging”. Amoxicillin was chosen to be the first antimicrobial for this study. The drug was labeled with [<jats:sup>62</jats:sup>Zn/<jats:sup>65</jats:sup>Zn] ZnCl<jats:sub>2</jats:sub>. Radiolabelled amoxicillin and non-labeled amoxicillin were administrated to rainbow trout fish simultaneously. To enable visualization of the remaining residues of amoxicillin in fish, <jats:italic>In-vivo</jats:italic> positron emission tomography (PET) imaging was done at different intervals from 30 min to 21 days after administration. Evaluation of the amount of radiolabelled amoxicillin in fish was done using a high purity germanium (HPGe) nuclear detector, and enzyme linked immunosorbent assay (ELISA) technique was used for the non-labeled drug. In this study, a comprehensive method for in-house production of zinc radioisotopes was also included. The results showed that depletion imaging and biodistribution study based on gamma spectroscopy of radionuclides in tissues, is a precise method for accurate understanding of the drug’s distribution, metabolic and excretory profile.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-02-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139772950","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. Mehedi Hasan, M. Shuza Uddin, A. Kumer Chakroborty, M. Shamsuzzoha Basunia
Excitation functions for the formation of the radionuclides 51Cr, 52Mn and 54Mn via deuteron-induced activation of natural iron were measured up to deuteron energies of 35 MeV. The available experimental databases of the reaction products 51Cr, 52Mn and 54Mn were extended and compared with the nuclear model calculations using the TALYS code. The model calculations reproduce our measured data after a careful choice of the input model parameters. Some information obtained on competition between the emission of multinucleons and a bound α-particle.
{"title":"Activation cross sections for the formation of 51Cr and 52,54Mn in interactions of deuterons with iron","authors":"M. Mehedi Hasan, M. Shuza Uddin, A. Kumer Chakroborty, M. Shamsuzzoha Basunia","doi":"10.1515/ract-2023-0259","DOIUrl":"https://doi.org/10.1515/ract-2023-0259","url":null,"abstract":"Excitation functions for the formation of the radionuclides <jats:sup>51</jats:sup>Cr, <jats:sup>52</jats:sup>Mn and <jats:sup>54</jats:sup>Mn via deuteron-induced activation of natural iron were measured up to deuteron energies of 35 MeV. The available experimental databases of the reaction products <jats:sup>51</jats:sup>Cr, <jats:sup>52</jats:sup>Mn and <jats:sup>54</jats:sup>Mn were extended and compared with the nuclear model calculations using the TALYS code. The model calculations reproduce our measured data after a careful choice of the input model parameters. Some information obtained on competition between the emission of multinucleons and a bound α-particle.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759122","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}
S. Chattopadhyay, Samarjit Singha, Shayantani Ash, Luna Barua, Devaraj G. Mahesh, Sujata SahaDas, Madhusmita, Md. Nayer Alam, Umesh Kumar, Suprakash Roy, Prosenjit Dhang, S. Dey
Gallium-68 [t 1/2: 67.7 min, β+ (89 %)] has application in PET imaging mainly for prostate cancer and neuroendocrine tumours. Gallium-68 is generally obtained from a 68Ge/68Ga generator. It is therefore an important task to prepare 68Ge (t 1/2 = 271 days) radiochemical for the manufacture of 68Ge/68Ga generator to cater for the needs of various nuclear medicine centres. Germanium-68 has been produced successfully after irradiation of indigenously developed Ga–Ni targets in a 30 MeV cyclotron and chemical processing of the irradiated targets using an indigenous semi-automated module. The Ga–Ni targets were prepared by an electroplating method. The 68Ge has been radiochemically separated from irradiated Ga–Ni targets using Sephadex G-25 column chromatography. The chemical separation yield and radionuclidic purity of 68Ge were about 70 % (n = 3) and about 98.3 % (n = 3), respectively.
{"title":"Production and radiochemical separation of 68Ge from irradiated Ga–Ni alloy target in 30 MeV cyclotron","authors":"S. Chattopadhyay, Samarjit Singha, Shayantani Ash, Luna Barua, Devaraj G. Mahesh, Sujata SahaDas, Madhusmita, Md. Nayer Alam, Umesh Kumar, Suprakash Roy, Prosenjit Dhang, S. Dey","doi":"10.1515/ract-2023-0195","DOIUrl":"https://doi.org/10.1515/ract-2023-0195","url":null,"abstract":"\u0000 Gallium-68 [t\u0000 1/2: 67.7 min, β+ (89 %)] has application in PET imaging mainly for prostate cancer and neuroendocrine tumours. Gallium-68 is generally obtained from a 68Ge/68Ga generator. It is therefore an important task to prepare 68Ge (t\u0000 1/2 = 271 days) radiochemical for the manufacture of 68Ge/68Ga generator to cater for the needs of various nuclear medicine centres. Germanium-68 has been produced successfully after irradiation of indigenously developed Ga–Ni targets in a 30 MeV cyclotron and chemical processing of the irradiated targets using an indigenous semi-automated module. The Ga–Ni targets were prepared by an electroplating method. The 68Ge has been radiochemically separated from irradiated Ga–Ni targets using Sephadex G-25 column chromatography. The chemical separation yield and radionuclidic purity of 68Ge were about 70 % (n = 3) and about 98.3 % (n = 3), respectively.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139837024","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}
Increasing population, food demands and climatic stressors pose an imminent threat to groundwater sustainability in regional aquifer systems globally. Limited availability of surface water and erratic/uncertain rainfall necessitates preservation of groundwater resources, which form reliable fresh water reserves in most of the arid regions. Bhuj Sandstone aquifer is one such fresh groundwater systems in Western India catering the domestic/irrigational needs for over 2 million population. Rapid groundwater depletion in this area warranted a mandatory conservation of groundwater resources for future sustainability. Nuclear techniques using 3H and 14C provide estimates of groundwater age that help in planning sustainable groundwater management. In this study, sustainability of deep groundwater was assessed using environmental radioactive isotopes (3H, 14C). Results indicate that 14C activity of the groundwater samples varies from 26 to 73.6 pMC (percent modern carbon). Considering the various biases and uncertainties present, multiple correction models were applied to obtain representative groundwater ages by incorporating stable (13C) isotope and hydrogeochemical data. The corrected and representative ages are found to range from 5.8 to 8.6 ka BP (thousand years before present). From the study it can be inferred that central Bhuj aquifer hosts paleo-groundwater while the western part is recently recharged. Therefore, over-exploitation of deep groundwater in central Bhuj aquifer may further lower the water levels and this would have long-term impact on the socio-economic development of Kutch region.
{"title":"Evaluating sustainability of Bhuj aquifer system, Western India using nuclear dating techniques","authors":"Annadasankar Roy, Uday Kumar Sinha, Bharatkumar Hathi, Sitangshu Chatterjee, Diksha Pant, Hemant Mohokar, Ajay Jaryal, Harish Jagat Pant, Dipankar Saha, Ratan Jain, Tirumalesh Keesari","doi":"10.1515/ract-2023-0198","DOIUrl":"https://doi.org/10.1515/ract-2023-0198","url":null,"abstract":"Increasing population, food demands and climatic stressors pose an imminent threat to groundwater sustainability in regional aquifer systems globally. Limited availability of surface water and erratic/uncertain rainfall necessitates preservation of groundwater resources, which form reliable fresh water reserves in most of the arid regions. Bhuj Sandstone aquifer is one such fresh groundwater systems in Western India catering the domestic/irrigational needs for over 2 million population. Rapid groundwater depletion in this area warranted a mandatory conservation of groundwater resources for future sustainability. Nuclear techniques using <jats:sup>3</jats:sup>H and <jats:sup>14</jats:sup>C provide estimates of groundwater age that help in planning sustainable groundwater management. In this study, sustainability of deep groundwater was assessed using environmental radioactive isotopes (<jats:sup>3</jats:sup>H, <jats:sup>14</jats:sup>C). Results indicate that <jats:sup>14</jats:sup>C activity of the groundwater samples varies from 26 to 73.6 pMC (percent modern carbon). Considering the various biases and uncertainties present, multiple correction models were applied to obtain representative groundwater ages by incorporating stable (<jats:sup>13</jats:sup>C) isotope and hydrogeochemical data. The corrected and representative ages are found to range from 5.8 to 8.6 ka BP (thousand years before present). From the study it can be inferred that central Bhuj aquifer hosts paleo-groundwater while the western part is recently recharged. Therefore, over-exploitation of deep groundwater in central Bhuj aquifer may further lower the water levels and this would have long-term impact on the socio-economic development of Kutch region.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759128","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}
The production method of no-carrier added Lutetium-177 (177Lu) was developed from a neutron-activated natural ytterbium (Yb) using column chromatography separation method. Dowex W50 X8 resin and a combination of alpha-hydroxyisobutyric acid (α-HIBA) and hydrochloric acid (HCl) were used as column filler and eluent, respectively. HCl increased the desorption and separation between 177Lu and Yb at a concentration of 0.25 M, while the optimal α-HIBA concentration was 0.15 M, resulting in 177Lu yield of 81.19 % and low impurities (175Yb: 9.28 %, and 169Yb: 2.09 %). Nevertheless, further study using an enriched 176Yb target is essential to significantly increase the specific activity of 177Lu.
{"title":"Alpha-hydroxyisobutyric acid-assisted solid-liquid chromatography for the separation of lutetium-177 from neutron-irradiated natural ytterbium","authors":"Aulia Arivin Billah, Kukuh Eka Prasetya, Fany Triyatna, Daya Agung Sarwono, Abidin Abidin, Fernanto Rindiyantono, Maiyesni Maiyesni, Miftakul Munir, Indra Saptiama, Rien Ritawidya, Agustino Zulys","doi":"10.1515/ract-2023-0234","DOIUrl":"https://doi.org/10.1515/ract-2023-0234","url":null,"abstract":"The production method of no-carrier added Lutetium-177 (<jats:sup>177</jats:sup>Lu) was developed from a neutron-activated natural ytterbium (Yb) using column chromatography separation method. Dowex W50 X8 resin and a combination of alpha-hydroxyisobutyric acid (α-HIBA) and hydrochloric acid (HCl) were used as column filler and eluent, respectively. HCl increased the desorption and separation between <jats:sup>177</jats:sup>Lu and Yb at a concentration of 0.25 M, while the optimal α-HIBA concentration was 0.15 M, resulting in <jats:sup>177</jats:sup>Lu yield of 81.19 % and low impurities (<jats:sup>175</jats:sup>Yb: 9.28 %, and <jats:sup>169</jats:sup>Yb: 2.09 %). Nevertheless, further study using an enriched <jats:sup>176</jats:sup>Yb target is essential to significantly increase the specific activity of <jats:sup>177</jats:sup>Lu.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759245","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}
Gamma-ray spectrometry-based isotopic composition analysis is a prerequisite for absolute non-destructive assay of Pu by neutron counting or calorimetry. However, gamma-ray spectrometry can be complicated in samples that are heavily shielded or have a high 241Am fraction. Herein, for the absolute non-destructive assay of Pu, a simple yet potent empirical methodology combining neutron multiplicity counting and calorimetry is proposed, which obviates the need for gamma-ray spectrometry-based isotopic composition analysis. The approach includes stepwise correlation between the parameters obtained from neutron multiplicity counting, i.e., α ((α, n) neutron to spontaneous fission neutron ratio), effective mass of 240Pu, and D (doubles neutron rate) with the thermal power output (WPu) due to radioactive decay (measured by calorimetry). Because D and WPu both are governed by the Pu isotopic composition, their correlation should be sensitive to the isotopic information in a given sample. Mandatory correction for the 241Am contribution in WPu was done using the linear plot between its weight fraction and the corresponding α. The proposed methodology was validated by analyzing several PuO2 standards containing high 241Am fraction (0.02–0.09). The measured Pu amounts were within 8 % of the actual values with measurement uncertainties between 8 and 10 %, which shows the potential of the proposed methodology for the assay of samples having high 241Am content or for the quantification of Pu in heavily shielded samples.
基于伽马射线光谱法的同位素组成分析是通过中子计数法或量热法对钚进行绝对无损化验的先决条件。然而，对于屏蔽较强或 241Am 含量较高的样品，伽马射线光谱分析可能比较复杂。本文提出了一种结合中子倍率计数法和量热法的简单而有效的经验方法，用于钚的绝对无损检测，从而避免了基于伽马射线光谱法的同位素组成分析。该方法包括逐步将中子倍率计数获得的参数，即α（（α，n）中子与自发裂变中子比）、240Pu 的有效质量和 D（倍率中子）与放射性衰变产生的热功率输出（W Pu）（通过量热计测量）进行关联。由于 D 和 W Pu 都受 Pu 同位素组成的影响，因此它们之间的相关性对特定样品中的同位素信息非常敏感。通过分析几种含有高 241Am 分数（0.02-0.09）的二氧化钚标准样品，对所提出的方法进行了验证。测得的钚含量在实际值的 8% 以内，测量不确定性在 8% 到 10% 之间，这表明所提出的方法有潜力用于检测 241Am 含量较高的样品或用于定量重屏蔽样品中的钚。
{"title":"Non-destructive assay of plutonium in absence of gamma-ray spectrometry","authors":"Sanhita Chaudhury, Ashwani Kumar, Sabyasachi Patra, Rahul Tripathi","doi":"10.1515/ract-2023-0193","DOIUrl":"https://doi.org/10.1515/ract-2023-0193","url":null,"abstract":"Gamma-ray spectrometry-based isotopic composition analysis is a prerequisite for absolute non-destructive assay of Pu by neutron counting or calorimetry. However, gamma-ray spectrometry can be complicated in samples that are heavily shielded or have a high <jats:sup>241</jats:sup>Am fraction. Herein, for the absolute non-destructive assay of Pu, a simple yet potent empirical methodology combining neutron multiplicity counting and calorimetry is proposed, which obviates the need for gamma-ray spectrometry-based isotopic composition analysis. The approach includes stepwise correlation between the parameters obtained from neutron multiplicity counting, i.e., <jats:italic>α</jats:italic> ((<jats:italic>α</jats:italic>, <jats:italic>n</jats:italic>) neutron to spontaneous fission neutron ratio), effective mass of <jats:sup>240</jats:sup>Pu, and D (doubles neutron rate) with the thermal power output (<jats:italic>W</jats:italic> <jats:sub>Pu</jats:sub>) due to radioactive decay (measured by calorimetry). Because D and <jats:italic>W</jats:italic> <jats:sub>Pu</jats:sub> both are governed by the Pu isotopic composition, their correlation should be sensitive to the isotopic information in a given sample. Mandatory correction for the <jats:sup>241</jats:sup>Am contribution in <jats:italic>W</jats:italic> <jats:sub>Pu</jats:sub> was done using the linear plot between its weight fraction and the corresponding <jats:italic>α</jats:italic>. The proposed methodology was validated by analyzing several PuO<jats:sub>2</jats:sub> standards containing high <jats:sup>241</jats:sup>Am fraction (0.02–0.09). The measured Pu amounts were within 8 % of the actual values with measurement uncertainties between 8 and 10 %, which shows the potential of the proposed methodology for the assay of samples having high <jats:sup>241</jats:sup>Am content or for the quantification of Pu in heavily shielded samples.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759242","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}
This report unveils the outcomes of measurements of 222Rn exhalation rates, effective 226Ra content, and the annual effective dose for rocks and soil collected in the vicinity and far from the seismically active Kopili Fault Zone, India. LR-115 (II) nuclear track detector has been used to investigate radiation exposure in the seismically active fault zone and gneissic complex of the Shillong Plateau, which have significant geological characteristics and frequently produce earthquakes. In this study, 222Rn mass exhalation rates for granite, gneiss, and soil samples collected near and far from the fault were calculated to be in the ranges of 73.2–83.0, 11.0–14.8, 21.1–70.7 and 34.3–65.5, 6.4–9.9, 19.1–28.9 mBq kg−1 h−1, respectively. Surface exhalation rates of 222Rn for granite, gneiss, and soil samples collected near and far from the fault varied between 2428.8–2751.7, 365.6–491.9, 698.3–2345.9, and 1138.6–2172.7, 211.9–328.2, 634.9–960.0 mBq m−2 h−1, respectively. The 226Ra contents of granite, gneiss, and soil collected in similar distributions were found to vary from 9.76–11.06, 1.47–1.98, 2.8–9.4, and 4.58–8.74, 0.85–1.32, 2.6–3.6 Bq kg−1, respectively. The annual effective doses attributed to 222Rn inhalation from exposure to the samples were calculated to be in the ranges of 176.3–199.8, 26.5–35.7, 50.7–170.3 and 82.7–157.7, 15.4–23.8, 46.1–69.7 μSv y−1, respectively, for granite, gneiss, and soil. The lifetime fatality-risks have also been analysed in this study. The samples that were collected in close proximity to the fault showed higher values than those that were collected farther away. However, the results reveal that the measured values are within the globally recognised permissible range.
{"title":"Measurements of 222Rn exhalation rates, effective 226Ra contents, and radiological risks from geological samples of Kopili Fault Zone and gneissic complex of Shillong Plateau, India","authors":"Pranjal Protim Gogoi, Sarat Phukan, Debajyoti Barooah","doi":"10.1515/ract-2023-0232","DOIUrl":"https://doi.org/10.1515/ract-2023-0232","url":null,"abstract":"This report unveils the outcomes of measurements of <jats:sup>222</jats:sup>Rn exhalation rates, effective <jats:sup>226</jats:sup>Ra content, and the annual effective dose for rocks and soil collected in the vicinity and far from the seismically active Kopili Fault Zone, India. LR-115 (II) nuclear track detector has been used to investigate radiation exposure in the seismically active fault zone and gneissic complex of the Shillong Plateau, which have significant geological characteristics and frequently produce earthquakes. In this study, <jats:sup>222</jats:sup>Rn mass exhalation rates for granite, gneiss, and soil samples collected near and far from the fault were calculated to be in the ranges of 73.2–83.0, 11.0–14.8, 21.1–70.7 and 34.3–65.5, 6.4–9.9, 19.1–28.9 mBq kg<jats:sup>−1</jats:sup> h<jats:sup>−1</jats:sup>, respectively. Surface exhalation rates of <jats:sup>222</jats:sup>Rn for granite, gneiss, and soil samples collected near and far from the fault varied between 2428.8–2751.7, 365.6–491.9, 698.3–2345.9, and 1138.6–2172.7, 211.9–328.2, 634.9–960.0 mBq m<jats:sup>−2</jats:sup> h<jats:sup>−1</jats:sup>, respectively. The <jats:sup>226</jats:sup>Ra contents of granite, gneiss, and soil collected in similar distributions were found to vary from 9.76–11.06, 1.47–1.98, 2.8–9.4, and 4.58–8.74, 0.85–1.32, 2.6–3.6 Bq kg<jats:sup>−1</jats:sup>, respectively. The annual effective doses attributed to <jats:sup>222</jats:sup>Rn inhalation from exposure to the samples were calculated to be in the ranges of 176.3–199.8, 26.5–35.7, 50.7–170.3 and 82.7–157.7, 15.4–23.8, 46.1–69.7 μSv y<jats:sup>−1</jats:sup>, respectively, for granite, gneiss, and soil. The lifetime fatality-risks have also been analysed in this study. The samples that were collected in close proximity to the fault showed higher values than those that were collected farther away. However, the results reveal that the measured values are within the globally recognised permissible range.","PeriodicalId":21167,"journal":{"name":"Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":1.8,"publicationDate":"2024-02-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139759249","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}
京公网安备 11010802042870号
京ICP备2023020795号-1
扫码关注我们
求助内容：
应助结果提醒方式：