We prepared Nd-doped CaYAl3O7 single crystals with different Nd concentrations of 0.1, 0.5, 1.0, 5.0, 10, and 20% by the floating zone method. Photoluminescence (PL) and scintillation properties of all the samples were investigated, and the performance as near-infrared (NIR) scintillators was evaluated. All the samples exhibited some luminescence peaks of 4f-4f transitions of Nd3+ in PL and scintillation spectra at around 890, 1060, and 1300 nm. The 5.0% Nd-doped sample showed the highest PL quantum yield of 49.5%. In addition, the 5.0% Nd-doped sample had the highest scintillation intensity under X-ray irradiation among the samples, and the lowest detectable dose rate was 0.001 Gy/h.
{"title":"Near-infrared scintillation properties of Nd-doped CaYAl3O7 single crystals","authors":"Akihiro Nishikawa, Kensei Ichiba, Takumi Kato, Daisuke Nakauchi, Noriaki Kawaguchi, Takayuki Yanagida","doi":"10.1016/j.apradiso.2024.111559","DOIUrl":"10.1016/j.apradiso.2024.111559","url":null,"abstract":"<div><div>We prepared Nd-doped CaYAl<sub>3</sub>O<sub>7</sub> single crystals with different Nd concentrations of 0.1, 0.5, 1.0, 5.0, 10, and 20% by the floating zone method. Photoluminescence (PL) and scintillation properties of all the samples were investigated, and the performance as near-infrared (NIR) scintillators was evaluated. All the samples exhibited some luminescence peaks of 4f-4f transitions of Nd<sup>3+</sup> in PL and scintillation spectra at around 890, 1060, and 1300 nm. The 5.0% Nd-doped sample showed the highest PL quantum yield of 49.5%. In addition, the 5.0% Nd-doped sample had the highest scintillation intensity under X-ray irradiation among the samples, and the lowest detectable dose rate was 0.001 Gy/h.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111559"},"PeriodicalIF":1.6,"publicationDate":"2024-10-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142493510","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-19DOI: 10.1016/j.apradiso.2024.111558
Minal Y. Nadar, S. Halder, L. Mishra, D.K. Akar, I.S. Singh, P.D. Sawant, P. Chaudhury
Bioassay of radiation workers handling actinides in powder form is carried out annually under routine monitoring program. In case of routine monitoring, as the day of intake is unknown, it is assumed that intake has occurred at the midpoint of monitoring interval. However, an uncertainty is introduced in intake estimation due to this assumption. In the present work, uncertainties were evaluated due to unknown time of intake of Type M and S compounds of Pu and U for annual and biennial monitoring interval. Lung and excreta monitoring methods were considered for uncertainty estimation along with the spread of ±1 month or ±2 months in measurements, at the end of monitoring interval. Annual lung monitoring is found to be the most robust and accurate method for assessment of intake of Type S compounds of Pu, Am and U when time of intake is unknown and Pu is detected using 241Am as a tracer. For Type M compounds, uncertainty was found to be higher than 3 for biennial monitoring interval. Uncertainty is found to be less than 3 for Type S compounds of Pu and U and also for Type M compounds of Pu for both, annual and biennial monitoring intervals using urine analysis. It is higher than 3 for Type M compounds of U for both the monitoring intervals. It is greater than 3 for both Type M and S compounds of Pu and U for both the monitoring intervals using fecal analysis.
在例行监测计划下，每年都会对处理粉末状锕系元素的辐射工作人员进行生物测定。在例行监测中，由于摄入日不详，因此假定摄入发生在监测间隔的中点。然而，由于这一假设，在摄入量估算中引入了不确定性。在本研究中，由于每年和每两年监测一次钚和铀的 M 型和 S 型化合物的未知摄入时间，对不确定性进行了评估。在估算不确定性时，考虑了肺和排泄物监测方法以及监测间隔结束时测量值的±1 个月或 ±2 个月的差值。当摄入时间未知，并使用 241Am 作为示踪剂检测钚时，发现年度肺监测是评估钚、镅和铀的 S 类化合物摄入量的最可靠、最准确的方法。就 M 类化合物而言，两年监测一次的不确定性大于 3。对于钚和铀的 S 类化合物以及钚的 M 类化合物，在使用尿液分析进行年度和双年度监测时，不确定性均小于 3。在两个监测周期内，M 类 U 化合物的不确定性均大于 3。利用粪便分析法，在两个监测周期内，钚和铀的 M 型和 S 型化合物的含量均大于 3。
{"title":"Estimating Uncertainty in Actinide Intake Due to Unknown Time of Exposure","authors":"Minal Y. Nadar, S. Halder, L. Mishra, D.K. Akar, I.S. Singh, P.D. Sawant, P. Chaudhury","doi":"10.1016/j.apradiso.2024.111558","DOIUrl":"10.1016/j.apradiso.2024.111558","url":null,"abstract":"<div><div>Bioassay of radiation workers handling actinides in powder form is carried out annually under routine monitoring program. In case of routine monitoring, as the day of intake is unknown, it is assumed that intake has occurred at the midpoint of monitoring interval. However, an uncertainty is introduced in intake estimation due to this assumption. In the present work, uncertainties were evaluated due to unknown time of intake of Type M and S compounds of Pu and U for annual and biennial monitoring interval. Lung and excreta monitoring methods were considered for uncertainty estimation along with the spread of ±1 month or ±2 months in measurements, at the end of monitoring interval. Annual lung monitoring is found to be the most robust and accurate method for assessment of intake of Type S compounds of Pu, Am and U when time of intake is unknown and Pu is detected using <sup>241</sup>Am as a tracer. For Type M compounds, uncertainty was found to be higher than 3 for biennial monitoring interval. Uncertainty is found to be less than 3 for Type S compounds of Pu and U and also for Type M compounds of Pu for both, annual and biennial monitoring intervals using urine analysis. It is higher than 3 for Type M compounds of U for both the monitoring intervals. It is greater than 3 for both Type M and S compounds of Pu and U for both the monitoring intervals using fecal analysis.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111558"},"PeriodicalIF":1.6,"publicationDate":"2024-10-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142493509","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-18DOI: 10.1016/j.apradiso.2024.111557
Joel M. Santos , Luiza M. Balieiro , Rodrigo S. Santos , Margareth M.N. Matsuda , Elaine B. Araújo
The Energy and Nuclear Research Institute (IPEN) is studying the production of the radiopharmaceutical [177Lu]Lu-PSMA I&T, in accordance with the good manufacturing practices recommended by the National Health Surveillance Agency (ANVISA), to be used in the therapy of prostate cancer. This work aims to validate chromatographic methods, Thin-Layer Chromatographic (TLC) and high-performance liquid chromatography (HPLC), to determine the radiochemical purity (RCP) of the product. The entire validation process of this work was based on ANVISA's RDC 166, 2017 and the Guide 10, version 1, 2017, guided the statistical treatments adopted. With the selectivity study we can observe that the presence of impurities or excess excipients in the sample does not interfere with the quantification of the product. The proposed methods were linear with linear correlation coefficients (r) above 0.99. The precision and repeatability presented relative standard deviation values lower than specified (RSD <5 %). The small controlled variations in the method suggested for the robustness test also did not affect the radiochemical purity of the product. In view of the results and in accordance with the criteria established by the National Health Surveillance Agency (ANVISA), the two chromatographic methods were validated in accordance with RDC 166, 2017, proving to be selective, precise, linear and robust. The validation of TLC and HPLC methods enables their application in the batch release routine of the new radiopharmaceutical at Radiopharmacy Center of IPEN.
{"title":"Validation of chromatographic methods, TLC and HPLC, to quantify known radiochemical impurities and the radiochemical purity the radiopharmaceutical [177Lu]Lu-PSMA I&T","authors":"Joel M. Santos , Luiza M. Balieiro , Rodrigo S. Santos , Margareth M.N. Matsuda , Elaine B. Araújo","doi":"10.1016/j.apradiso.2024.111557","DOIUrl":"10.1016/j.apradiso.2024.111557","url":null,"abstract":"<div><div>The Energy and Nuclear Research Institute (IPEN) is studying the production of the radiopharmaceutical [<sup>177</sup>Lu]Lu-PSMA I&T, in accordance with the good manufacturing practices recommended by the National Health Surveillance Agency (ANVISA), to be used in the therapy of prostate cancer. This work aims to validate chromatographic methods, Thin-Layer Chromatographic (TLC) and high-performance liquid chromatography (HPLC), to determine the radiochemical purity (RCP) of the product. The entire validation process of this work was based on ANVISA's RDC 166, 2017 and the Guide 10, version 1, 2017, guided the statistical treatments adopted. With the selectivity study we can observe that the presence of impurities or excess excipients in the sample does not interfere with the quantification of the product. The proposed methods were linear with linear correlation coefficients (r) above 0.99. The precision and repeatability presented relative standard deviation values lower than specified (RSD <5 %). The small controlled variations in the method suggested for the robustness test also did not affect the radiochemical purity of the product. In view of the results and in accordance with the criteria established by the National Health Surveillance Agency (ANVISA), the two chromatographic methods were validated in accordance with RDC 166, 2017, proving to be selective, precise, linear and robust. The validation of TLC and HPLC methods enables their application in the batch release routine of the new radiopharmaceutical at Radiopharmacy Center of IPEN.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111557"},"PeriodicalIF":1.6,"publicationDate":"2024-10-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142531822","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-18DOI: 10.1016/j.apradiso.2024.111553
Yanxia Cheng , Bo Li , Yingjiang Hu , Zuobiao Liu , Ning Luo , Yunming Chen , Jingsong Zhang
As one of the most important integrated nuclides for diagnosis and treatment in recent years, rhenium-188 (188Re) has a broad scope in the clinical application. Due to the specific properties of such radionuclide, it was mainly provided by the chromatographic 188W-188Re generators. There is no doubt that the application of 188Re in the treatment of various diseases depended on the development of 188W-188Re generator. Considering the high standards of such technology on radioactive activity of 188W and impurity content, a 188W-188Re generator filled with the zirconium tungstate gel has been prepared in this work. The effects of molar ratio of chemical agents, pH, reaction temperature, drying methods, rinsing methods and other conditions on the synthesis of gel particles have been studied. Furthermore, a variety of characterization techniques were used to observe the macro-/micro-morphology and chemical structure of gel particles. It can be concluded that vacuum freeze-dried method could significantly increase the specific surface area, pore size and tungsten content of gel particle. In order to decrease the content of 188W in the elute, a handful of acidic alumina was filled in the bottom of our 188W-188Re generator, an elution and purification integrated-generator was formed. During the first five processes, the nuclear purity of 188Re solution was above 99.99%, the radiochemical purity was approximately 99.5%, the pH value was 5.0–7.0 and the average elution efficiency reached up to 82.7%. In addition, the leakage rate of 188W was low as 1.60 × 10−6, and the peak of elute curve was located at 2 mL without the trailing phenomenon. This work lays a solid foundation for the domestic demand of daughter nuclide 188Re, further makes an outstanding contribution to the application of the radiation therapy technology and the protection of people's health.
{"title":"Investigation on preparation and properties of gel type 188W/188Re generator","authors":"Yanxia Cheng , Bo Li , Yingjiang Hu , Zuobiao Liu , Ning Luo , Yunming Chen , Jingsong Zhang","doi":"10.1016/j.apradiso.2024.111553","DOIUrl":"10.1016/j.apradiso.2024.111553","url":null,"abstract":"<div><div>As one of the most important integrated nuclides for diagnosis and treatment in recent years, rhenium-188 (<sup>188</sup>Re) has a broad scope in the clinical application. Due to the specific properties of such radionuclide, it was mainly provided by the chromatographic <sup>188</sup>W-<sup>188</sup>Re generators. There is no doubt that the application of <sup>188</sup>Re in the treatment of various diseases depended on the development of <sup>188</sup>W-<sup>188</sup>Re generator. Considering the high standards of such technology on radioactive activity of <sup>188</sup>W and impurity content, a <sup>188</sup>W-<sup>188</sup>Re generator filled with the zirconium tungstate gel has been prepared in this work. The effects of molar ratio of chemical agents, pH, reaction temperature, drying methods, rinsing methods and other conditions on the synthesis of gel particles have been studied. Furthermore, a variety of characterization techniques were used to observe the macro-/micro-morphology and chemical structure of gel particles. It can be concluded that vacuum freeze-dried method could significantly increase the specific surface area, pore size and tungsten content of gel particle. In order to decrease the content of <sup>188</sup>W in the elute, a handful of acidic alumina was filled in the bottom of our <sup>188</sup>W-<sup>188</sup>Re generator, an elution and purification integrated-generator was formed. During the first five processes, the nuclear purity of <sup>188</sup>Re solution was above 99.99%, the radiochemical purity was approximately 99.5%, the pH value was 5.0–7.0 and the average elution efficiency reached up to 82.7%. In addition, the leakage rate of <sup>188</sup>W was low as 1.60 × 10<sup>−6</sup>, and the peak of elute curve was located at 2 mL without the trailing phenomenon. This work lays a solid foundation for the domestic demand of daughter nuclide <sup>188</sup>Re, further makes an outstanding contribution to the application of the radiation therapy technology and the protection of people's health.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111553"},"PeriodicalIF":1.6,"publicationDate":"2024-10-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142456675","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-18DOI: 10.1016/j.apradiso.2024.111551
Ursula Søndergaard , Kolle E. Thomas , Kristina Søborg Pedersen , Mathias Kranz , Rune Sundset , Angel Moldes-Anaya , Mikael Jensen
Clinical advancements in nuclear medicine theranostics has excited a research interest in exploring novel radionuclides for medical use. The duo of the β− emitter 67Cu and the positron emitter 64Cu, has advantages over the well-established clinical pair 68Ga and 177Lu in terms of capability for high-precision therapy. Low availability has hindered the use of 67Cu whereas 64Cu has become established at a limited number of sites through production in low-to-medium energy biomedical cyclotrons. Via the reaction 70Zn(p,α)67Cu, 67Cu can also be cyclotron produced, although data on the cross sections of this reaction are sparse. Our aim in this study was three-fold: 1) to establish cross sections for relevant beam energies (14–16 MeV) of the 70Zn(p,α)67Cu reaction; 2) determine experimentally the thick target yield for 16.5 MeV proton beam; 3) establish a routine production of 67Cu for radiochemical and preclinical research. Additionally, our work aims to explore the feasibility of using biomedical cyclotrons for developing of novel therapeutic radionuclides.
Thin layers of enriched 70Zn were electrodeposited onto silver foils to employ the stacked foils technique for assessing the cross section at six energies. The thick target yield was measured experimentally using a pressed [70Zn]ZnO target. Methods were developed for solid phase extraction separation of 67Cu from the target material, as well as quality control of the product with regards to radionuclidic and radiochemical purity. Radiolabelling of PSMA-617 precursor was performed and the end product injected in a healthy mouse for a kinetic study. As a proof of concept for preclinical applications The animal was then SPECT imaged using the 185 keV gamma emission line.
Summarizing, our data confirm that biomedical cyclotrons can contribute in developing novel radionuclides, even of low cross section, for preclinical research.
{"title":"Production of 67Cu at a biomedical cyclotron via 70Zn(p,α)67Cu reaction and its evaluation in a preclinical study using small animal SPECT/CT","authors":"Ursula Søndergaard , Kolle E. Thomas , Kristina Søborg Pedersen , Mathias Kranz , Rune Sundset , Angel Moldes-Anaya , Mikael Jensen","doi":"10.1016/j.apradiso.2024.111551","DOIUrl":"10.1016/j.apradiso.2024.111551","url":null,"abstract":"<div><div>Clinical advancements in nuclear medicine theranostics has excited a research interest in exploring novel radionuclides for medical use. The duo of the β<sup>−</sup> emitter <sup>67</sup>Cu and the positron emitter <sup>64</sup>Cu, has advantages over the well-established clinical pair <sup>68</sup>Ga and <sup>177</sup>Lu in terms of capability for high-precision therapy. Low availability has hindered the use of <sup>67</sup>Cu whereas <sup>64</sup>Cu has become established at a limited number of sites through production in low-to-medium energy biomedical cyclotrons. Via the reaction <sup>70</sup>Zn(p,α)<sup>67</sup>Cu, <sup>67</sup>Cu can also be cyclotron produced, although data on the cross sections of this reaction are sparse. Our aim in this study was three-fold: 1) to establish cross sections for relevant beam energies (14–16 MeV) of the <sup>70</sup>Zn(p,α)<sup>67</sup>Cu reaction; 2) determine experimentally the thick target yield for 16.5 MeV proton beam; 3) establish a routine production of <sup>67</sup>Cu for radiochemical and preclinical research. Additionally, our work aims to explore the feasibility of using biomedical cyclotrons for developing of novel therapeutic radionuclides.</div><div>Thin layers of enriched <sup>70</sup>Zn were electrodeposited onto silver foils to employ the stacked foils technique for assessing the cross section at six energies. The thick target yield was measured experimentally using a pressed [<sup>70</sup>Zn]ZnO target. Methods were developed for solid phase extraction separation of <sup>67</sup>Cu from the target material, as well as quality control of the product with regards to radionuclidic and radiochemical purity. Radiolabelling of PSMA-617 precursor was performed and the end product injected in a healthy mouse for a kinetic study. As a proof of concept for preclinical applications The animal was then SPECT imaged using the 185 keV gamma emission line.</div><div>Summarizing, our data confirm that biomedical cyclotrons can contribute in developing novel radionuclides, even of low cross section, for preclinical research.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"215 ","pages":"Article 111551"},"PeriodicalIF":1.6,"publicationDate":"2024-10-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142543302","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-18DOI: 10.1016/j.apradiso.2024.111552
Miloš Tichý , Ondřej Huml , Tomáš Bílý , Evžen Losa , Evžen Novák , Bohumil Jánský , Jiří Rejchrt
The neutron spectrum was measured at two locations in the spent fuel storage facility of the Temelín nuclear power plant. The measurement had two primary objectives: to map the neutron -γ field by quantifying the ambient dose equivalent H∗(10) and to identify methods that could improve the quality of the adjusted neutron spectrum using a Bonner Sphere Spectrometer (BSS). Three spectrometers were used: a BSS and two proton recoil spectrometers. Hydrogen-filled proportional counters and an EJ309 scintillator were used to construct the a priori spectrum for BSS adjustment. The details of this process and its results are discussed. The a posteriori spectrum was used to calculate the ambient dose equivalent H∗(10). The resulting spectrum is highly thermalised, but the predominant contribution to H∗(10) was in the 100 keV-1.3 MeV range. The use of hydrogen-proportional counters in combination with the BSS is recommended.
{"title":"Measurement of neutron spectra in spent fuel storage","authors":"Miloš Tichý , Ondřej Huml , Tomáš Bílý , Evžen Losa , Evžen Novák , Bohumil Jánský , Jiří Rejchrt","doi":"10.1016/j.apradiso.2024.111552","DOIUrl":"10.1016/j.apradiso.2024.111552","url":null,"abstract":"<div><div>The neutron spectrum was measured at two locations in the spent fuel storage facility of the Temelín nuclear power plant. The measurement had two primary objectives: to map the neutron -γ field by quantifying the ambient dose equivalent H∗(10) and to identify methods that could improve the quality of the adjusted neutron spectrum using a Bonner Sphere Spectrometer (BSS). Three spectrometers were used: a BSS and two proton recoil spectrometers. Hydrogen-filled proportional counters and an EJ309 scintillator were used to construct the a priori spectrum for BSS adjustment. The details of this process and its results are discussed. The a posteriori spectrum was used to calculate the ambient dose equivalent H∗(10). The resulting spectrum is highly thermalised, but the predominant contribution to H∗(10) was in the 100 keV-1.3 MeV range. The use of hydrogen-proportional counters in combination with the BSS is recommended.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111552"},"PeriodicalIF":1.6,"publicationDate":"2024-10-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142456676","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-16DOI: 10.1016/j.apradiso.2024.111533
Qi-Ze Liu , Wen-Han Dai , Ming Zeng , Zhi Zeng , V.F. Batyaev , K.V. Pavlov , A.Yu. Titarenko , Yu.E. Titarenko , R.S. Tikhonov , V.M. Zhivun
The accelerator-driven subcritical system (ADS) is a competitive option for next-generation nuclear energy systems. Production cross sections of long-lived residual radioactive nuclides in a proton-nuclide reaction are basic quantities for the calculation of accumulated radioactivity in the use of ADS systems. This work presents the production cross sections of 102mRh and 108mAg in a natural lead (natPb) target activated by 400 MeV protons. The natPb target was irradiated by a 400 MeV proton beam in NRC “Kurchatov Institute” and measured two decades later by a low background gamma spectrometer in China Jinping Underground Laboratory (CJPL). A spectrum analysis method based on simulated single-isotope spectrum and Bayesian peak fitting was employed to compute the activities and production cross sections of the residual nuclides. The experimentally measured cross-sections for 102mRh and 108mAg were 0.72 ± 0.05 mb and 0.76 ± 0.09 mb respectively. These values are approximately twice as high as those predicted by the QGSP_INCLXX_HP model and fall within the range predicted by the INCL4+ABLA and LAQGSM+GEM2 models for mass numbers A=102 and A=108. These findings offer new experimental insights for ADS research and provide a practical benchmark for theoretical models concerning proton-lead interactions.
{"title":"Production cross sections of 102mRh and 108mAg in proton bombed natPb target with 400 MeV energy","authors":"Qi-Ze Liu , Wen-Han Dai , Ming Zeng , Zhi Zeng , V.F. Batyaev , K.V. Pavlov , A.Yu. Titarenko , Yu.E. Titarenko , R.S. Tikhonov , V.M. Zhivun","doi":"10.1016/j.apradiso.2024.111533","DOIUrl":"10.1016/j.apradiso.2024.111533","url":null,"abstract":"<div><div>The accelerator-driven subcritical system (ADS) is a competitive option for next-generation nuclear energy systems. Production cross sections of long-lived residual radioactive nuclides in a proton-nuclide reaction are basic quantities for the calculation of accumulated radioactivity in the use of ADS systems. This work presents the production cross sections of <sup>102m</sup>Rh and <sup>108m</sup>Ag in a natural lead (<sup>nat</sup>Pb) target activated by 400 MeV protons. The <sup>nat</sup>Pb target was irradiated by a 400 MeV proton beam in NRC “Kurchatov Institute” and measured two decades later by a low background gamma spectrometer in China Jinping Underground Laboratory (CJPL). A spectrum analysis method based on simulated single-isotope spectrum and Bayesian peak fitting was employed to compute the activities and production cross sections of the residual nuclides. The experimentally measured cross-sections for <sup>102m</sup>Rh and <sup>108m</sup>Ag were 0.72 ± 0.05 mb and 0.76 ± 0.09 mb respectively. These values are approximately twice as high as those predicted by the QGSP_INCLXX_HP model and fall within the range predicted by the INCL4+ABLA and LAQGSM+GEM2 models for mass numbers A=102 and A=108. These findings offer new experimental insights for ADS research and provide a practical benchmark for theoretical models concerning proton-lead interactions.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111533"},"PeriodicalIF":1.6,"publicationDate":"2024-10-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142493528","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-15DOI: 10.1016/j.apradiso.2024.111554
Wei Jiang , Xixiang Yue , Sili Chen , Zhengke Zhang , Ji Wang , Jinsong Wang
With the development of nuclear industry, radioactive elements such as 137Cs put a threat on the water environment. It is a challenging task to remove the Cs+ in the nuclear wastewater. In the current study, we prepared a new Cs+-adsorbing material by introducing sulfhydryl group onto the surface of hollow mesoporous silica microspheres, then oxidizing the sulfhydryl group to sulfonic acid group. The obtained HMSS-SO3H material had an excellent adsorption capacity for Cs+ in the aqueous solution, with an adsorption capacity of 51.53 mg g−1 in 30 min. Characterization approaches, such as FT-IR and EDS, were used to confirm the result of modification. Adsorption experiments were carried out under. The influence of various parameters on the adsorption process was investigated under the conditions of changing pH, temperature, and time. The effect of competitive ions was also explored. The results indicated that the adsorption process followed the pseudo-second-order model and the main adsorption mechanisms are electrostatic interaction and coordination. The material had a best adsorption performance at a neutral pH. The adsorption process could well-fit the Langmuir's model, with a theoretical maximum adsorption capacity of 81.31 mg g−1. And the adsorption capacity was slightly affected by competing ions such as Mg2+ and Ca2+. The results indicate that the HMSS-SO3H prepared in this study is a promising adsorbent for Cs+, with the advantages of high adsorption capacity, fast adsorption rate and high selectivity.
{"title":"The adsorption of cesium by sulfonic acid functionalized hollow mesoporous silica microspheres","authors":"Wei Jiang , Xixiang Yue , Sili Chen , Zhengke Zhang , Ji Wang , Jinsong Wang","doi":"10.1016/j.apradiso.2024.111554","DOIUrl":"10.1016/j.apradiso.2024.111554","url":null,"abstract":"<div><div>With the development of nuclear industry, radioactive elements such as <sup>137</sup>Cs put a threat on the water environment. It is a challenging task to remove the Cs<sup>+</sup> in the nuclear wastewater. In the current study, we prepared a new Cs<sup>+</sup>-adsorbing material by introducing sulfhydryl group onto the surface of hollow mesoporous silica microspheres, then oxidizing the sulfhydryl group to sulfonic acid group. The obtained HMSS-SO<sub>3</sub>H material had an excellent adsorption capacity for Cs<sup>+</sup> in the aqueous solution, with an adsorption capacity of 51.53 mg g<sup>−1</sup> in 30 min. Characterization approaches, such as FT-IR and EDS, were used to confirm the result of modification. Adsorption experiments were carried out under. The influence of various parameters on the adsorption process was investigated under the conditions of changing pH, temperature, and time. The effect of competitive ions was also explored. The results indicated that the adsorption process followed the pseudo-second-order model and the main adsorption mechanisms are electrostatic interaction and coordination. The material had a best adsorption performance at a neutral pH. The adsorption process could well-fit the Langmuir's model, with a theoretical maximum adsorption capacity of 81.31 mg g<sup>−1</sup>. And the adsorption capacity was slightly affected by competing ions such as Mg<sup>2+</sup> and Ca<sup>2+</sup>. The results indicate that the HMSS-SO<sub>3</sub>H prepared in this study is a promising adsorbent for Cs<sup>+</sup>, with the advantages of high adsorption capacity, fast adsorption rate and high selectivity.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111554"},"PeriodicalIF":1.6,"publicationDate":"2024-10-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142444973","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-15DOI: 10.1016/j.apradiso.2024.111555
Jinlin Song , Xiaobin Tang , Pin Gong , Zhimeng Hu , Dajian Liang , Zeyu Wang , Peng Wang , Hong Ying , Haining Shi , Ao Liu , Zhifei Zhao , Song Bai
Silicon carbide (SiC) detectors have excellent radiation detection capabilities for various radiation particles, including high energy resolution, fast response times, and good radiation resistance. A SiC radiation detection system was developed to measure the neutron fluence rate and the γ-ray dose rate in high intensity radiation fields. The system was composed of two SiC detectors, a temperature monitor, two preamplifiers for each SiC detector, a data acquisition unit with two signal channels, three pairs of communication devices, and an application software to analyze and visualize the measurement data. The two SiC detectors were fabricated based on two kinds of 4H-SiC diodes and used to respectively respond to neutrons and γ-rays. Repeated experiments showed that the two SiC detectors of the system can respond to α-particles, neutrons, and γ-rays. To verify the performance of the SiC detection system, including the response linearity of the neutron fluence rate, the measurement range of the γ-ray dose rate, and the radiation resistance of the SiC radiation detectors, the system was tested in multiple neutron and γ-ray fields. The tests results show the system can measure the neutron fluence rate from 5.64 × 10 2 cm−2 s−1 to 1.03 × 10 5 cm−2 s−1 with excellent linearity response, and the γ-ray dose rate from 0.005 Gy/h to 20 Gy/h. Furthermore, the SiC detectors demonstrated good radiation resistance. The neutron and γ-ray radiation field can still be measured stably by the system after exposure to neutron fluence of 1.07 × 10 14 cm−2 and γ-ray dose of 3.52 × 10 4 Gy. This work is the preliminary research to continue the exploration how to measure the n/γ hybrid fields accurately using SiC detectors considering the different energy of neutrons.
{"title":"Development of a silicon carbide radiation detection system and experimentation of the system performance","authors":"Jinlin Song , Xiaobin Tang , Pin Gong , Zhimeng Hu , Dajian Liang , Zeyu Wang , Peng Wang , Hong Ying , Haining Shi , Ao Liu , Zhifei Zhao , Song Bai","doi":"10.1016/j.apradiso.2024.111555","DOIUrl":"10.1016/j.apradiso.2024.111555","url":null,"abstract":"<div><div>Silicon carbide (SiC) detectors have excellent radiation detection capabilities for various radiation particles, including high energy resolution, fast response times, and good radiation resistance. A SiC radiation detection system was developed to measure the neutron fluence rate and the γ-ray dose rate in high intensity radiation fields. The system was composed of two SiC detectors, a temperature monitor, two preamplifiers for each SiC detector, a data acquisition unit with two signal channels, three pairs of communication devices, and an application software to analyze and visualize the measurement data. The two SiC detectors were fabricated based on two kinds of 4H-SiC diodes and used to respectively respond to neutrons and γ-rays. Repeated experiments showed that the two SiC detectors of the system can respond to α-particles, neutrons, and γ-rays. To verify the performance of the SiC detection system, including the response linearity of the neutron fluence rate, the measurement range of the γ-ray dose rate, and the radiation resistance of the SiC radiation detectors, the system was tested in multiple neutron and γ-ray fields. The tests results show the system can measure the neutron fluence rate from 5.64 × 10 <sup>2</sup> cm<sup>−2</sup> s<sup>−1</sup> to 1.03 × 10 <sup>5</sup> cm<sup>−2</sup> s<sup>−1</sup> with excellent linearity response, and the γ-ray dose rate from 0.005 Gy/h to 20 Gy/h. Furthermore, the SiC detectors demonstrated good radiation resistance. The neutron and γ-ray radiation field can still be measured stably by the system after exposure to neutron fluence of 1.07 × 10 <sup>14</sup> cm<sup>−2</sup> and γ-ray dose of 3.52 × 10 <sup>4</sup> Gy. This work is the preliminary research to continue the exploration how to measure the n/γ hybrid fields accurately using SiC detectors considering the different energy of neutrons.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111555"},"PeriodicalIF":1.6,"publicationDate":"2024-10-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142444975","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-13DOI: 10.1016/j.apradiso.2024.111556
Shaymaa Mohammed Fayyadh , Ali Ben Ahmed
The results of the preparation of protective shields from ionizing radiation, flame retardant from pure epoxy supported by nano-bismuth oxide, show that the protective shields supported by nanoparticles improve the attenuation properties, the thermal stability, the flame retardancy and mechanical properties. Also, the polymeric shield supported by Bi2O3 (Na2CO3) retardant the flame much better than supported by Bi2O3 (NaOH). Finally, the quality of the protective shields increased as the energy of the photons of the ionizing rays decreased.
{"title":"Fabrication of polymeric shields to attenuation ionizing radiation and a flame retardant supported by nano-bismuth oxide prepared by co-deposition","authors":"Shaymaa Mohammed Fayyadh , Ali Ben Ahmed","doi":"10.1016/j.apradiso.2024.111556","DOIUrl":"10.1016/j.apradiso.2024.111556","url":null,"abstract":"<div><div>The results of the preparation of protective shields from ionizing radiation, flame retardant from pure epoxy supported by nano-bismuth oxide, show that the protective shields supported by nanoparticles improve the attenuation properties, the thermal stability, the flame retardancy and mechanical properties. Also, the polymeric shield supported by Bi<sub>2</sub>O<sub>3</sub> (Na<sub>2</sub>CO<sub>3</sub>) retardant the flame much better than supported by Bi<sub>2</sub>O<sub>3</sub> (NaOH). Finally, the quality of the protective shields increased as the energy of the photons of the ionizing rays decreased.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111556"},"PeriodicalIF":1.6,"publicationDate":"2024-10-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142444972","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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