Applied Radiation and Isotopes最新文献_第7页

Development and validation of a semi-automated [13N]Ammonia preparation system for clinical research 用于临床研究的半自动化[13N]氨制备系统的开发与验证

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-24 DOI: 10.1016/j.apradiso.2025.111861

Victor Amador Diaz, Peter M. Hall , Melissa J. Brown , Amy L. Vavere

{"title":"Development and validation of a semi-automated [13N]Ammonia preparation system for clinical research","authors":"Victor Amador Diaz, Peter M. Hall , Melissa J. Brown , Amy L. Vavere","doi":"10.1016/j.apradiso.2025.111861","DOIUrl":"10.1016/j.apradiso.2025.111861","url":null,"abstract":"<div><h3>Background/Objectives</h3><div>[<sup>13</sup>N]Ammonia is a PET tracer critical for cardiac perfusion imaging. Its manual production entails significant radiation exposure and labor inefficiencies. This study aimed to develop and validate a semi-automated purification module to enhance safety, reliability, and efficiency in clinical research settings.</div></div><div><h3>Methods</h3><div>The system employs microcontroller-based remote controls, carefully designed fluidic pathways, and an optimized module sterilization process. Iterative prototyping guided improvements, including compact hot cell-compatible dimensions, reduced cleaning times, and user-friendly features. Validation involved producing multiple [<sup>13</sup>N]ammonia batches assessed against FDA standards for radiochemical purity, sterility, and quality.</div></div><div><h3>Results</h3><div>The module consistently delivered [<sup>13</sup>N]ammonia with high radiochemical purity and compliance with all regulatory standards. Validation tests demonstrated reproducibility across consecutive batches, reducing operator intervention and radiation exposure. Features such as automated cleaning cycles and compact design enhanced operational efficiency and usability.</div></div><div><h3>Conclusions</h3><div>This semi-automated module offers a practical, low-cost solution for [<sup>13</sup>N]ammonia production in clinical research. Its design reduces operator exposure, increases reproducibility, and provides performance comparable to commercial synthesizers at a fraction of the cost. The system addresses the needs of facilities with limited throughput and infrastructure and serves as an accessible alternative to fully automated systems.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111861"},"PeriodicalIF":1.6,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868460","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}

引用次数: 0

Comparison of anteroposterior and posteroanterior projection in erect pelvic radiography 骨盆直立造影前后位投影的比较

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-24 DOI: 10.1016/j.apradiso.2025.111859

Amir Hajdarević , Nejc Mekiš

{"title":"Comparison of anteroposterior and posteroanterior projection in erect pelvic radiography","authors":"Amir Hajdarević , Nejc Mekiš","doi":"10.1016/j.apradiso.2025.111859","DOIUrl":"10.1016/j.apradiso.2025.111859","url":null,"abstract":"<div><h3>Purpose</h3><div>The X-ray examination of the pelvis is one of the procedures with the highest radiation dose and the most common X-ray examination. For this reason, this study investigated whether the alternative posteroanterior (PA) projection can be used instead of the established anteroposterior (AP) projection to perform pelvic radiography in an erect position.</div></div><div><h3>Methods</h3><div>The study was conducted in a clinical setting on 100 patients who were referred to erect pelvic radiography. The patients were randomly divided into two equal groups of 50; the first group was imaged in the AP projection, and the second group in the PA projection. Weight and height were measured for each patient, from which the body mass index was calculated. During imaging, the source-to-patient was measured, and the tube voltage, tube current and time product, Dose Area Product (DAP), source-to-image receptor distance, and primary field size were collated. Based on these data, the entrance surface dose (ESD) and the effective dose, as well as the dose to selected organs, were calculated. In addition to measured dosimetric values, image quality was also assessed by three experienced radiologists using ViewDEX 2.57 software.</div></div><div><h3>Results</h3><div>No statistically significant differences were found between the AP and PA projection of erect pelvic radiography for DAP and ESD. On the other hand, a statistically significant difference of 51.5 % (p < 0.001) was found when comparing the effective dose. There were no statistically significant differences between the image quality of the radiographs taken in the PA in AP projection.</div></div><div><h3>Conclusion</h3><div>Based on the above results, we can conclude that PA projection should be the method of choice when performing an erect pelvic radiography due to a significant decrease in effective dose.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111859"},"PeriodicalIF":1.6,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143895230","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}

引用次数: 0

Method for determining primary radiation shielding thickness of industrial X-ray-generating devices 工业x射线产生装置初级辐射屏蔽厚度的测定方法

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-23 DOI: 10.1016/j.apradiso.2025.111862

Byeonghyeon Park , Sangmin Lee , Eunjee Lee , Myeongji Kim , Hee Seo

{"title":"Method for determining primary radiation shielding thickness of industrial X-ray-generating devices","authors":"Byeonghyeon Park , Sangmin Lee , Eunjee Lee , Myeongji Kim , Hee Seo","doi":"10.1016/j.apradiso.2025.111862","DOIUrl":"10.1016/j.apradiso.2025.111862","url":null,"abstract":"<div><div>The United States National Council on Radiation Protection and Measurements (NCRP) and American National Standards Institute (ANSI)/Health Physics Society (HPS) reports typically are used as references during shielding evaluations of industrial X-ray-generating devices (XGDs). Considering the early date of publication of these reports, the types of some of the x-ray generators used in their experiments (i.e., generators for diagnosis, not industrial applications), the lack of available voltage types, and the non-intuitive application of the formulae, it is necessary to validate and improve the existing evaluation methods and data in consideration of the characteristics of industrial devices that are widely used today. To this end, we selected a representative industrial X-ray generator and measured its dose rate using a dose-rate meter with varying lead shielding thicknesses and tube voltages. By statistically analyzing the relationship between these variables, new formulae for shield-thickness evaluation according to fine tube-voltage increments, along with all of the related data, were derived. By using the information obtained in this study, the required lead thicknesses for industrial XGDs can be determined at different tube voltages in order to satisfy users’ dose-rate requirements and ensure the radiation safety of workers.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111862"},"PeriodicalIF":1.6,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143878904","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}

引用次数: 0

Constructing response surfaces with Kriging models for quick estimation of radionuclide activity in spent nuclear fuel 用克里格模型构建响应面，快速估计乏核燃料中放射性核素的活度

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-22 DOI: 10.1016/j.apradiso.2025.111858

Tai-Ting Huang, Tian-Tzuoh Lee

{"title":"Constructing response surfaces with Kriging models for quick estimation of radionuclide activity in spent nuclear fuel","authors":"Tai-Ting Huang, Tian-Tzuoh Lee","doi":"10.1016/j.apradiso.2025.111858","DOIUrl":"10.1016/j.apradiso.2025.111858","url":null,"abstract":"<div><div>Spent nuclear fuel discharged from the reactor core of a nuclear power plant at end of each operating cycle is usually temporarily stored in cooling pools and eventually will be placed in waste canisters buried 500 m below the surface. Over time, radioactive isotopes within these fuel assemblies continue to decay and release radiation, potentially posing risks to the biosphere. To address this concern, monitoring the variation in radioisotope activity with cooling time is essential.</div><div>This study explores an indirect method employing a Kriging model to construct response surfaces to perform a quick assessment of activity of key radioactive nuclides in spent nuclear fuel at various cooling times. Using data from Taiwan's Chinshan Nuclear Power Plant Unit 1 as an example, 1855 spent nuclear fuel assemblies were selected from a pool stored with 3390 fuel assemblies, based on parameters such as initial uranium-235 enrichment, total burnup, and specific power. The selected assemblies were then analyzed using SCALE 6.2 to calculate the activities of radioisotopes critical to safety, forming a comprehensive database.</div><div>Properly selected parameters enabled the establishment of an appropriate Kriging model. The process involved three major steps: initial sampling, Kriging model establishment for response surface estimation, and optimization based on maximum errors allowed. This iterative process resulted in the optimal Kriging model for estimating the response surface. The response surface considered four variables: specific power, initial uranium-235 enrichment, total burnup, and cooling time.</div><div>Validation of the Kriging models using spent nuclear fuel from Taiwan's Chinshan Power Plant and Kuosheng Power Plant showed that the response surfaces well-predicted the nuclide activity as it varies with cooling time, implying that the method may be used by the utility for safe and efficient management of nuclear waste.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111858"},"PeriodicalIF":1.6,"publicationDate":"2025-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143878575","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}

引用次数: 0

Analysis of acrylamide irradiation degradation effects and products in the starch mechanism 丙烯酰胺辐照降解淀粉的效果及产物机理分析

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-22 DOI: 10.1016/j.apradiso.2025.111860

Long Cui , Mengyuan Zhang , Xian Wang , Jun Xi , Liping Cheng , Mingcheng Yang , Dong Zhang , Huili Yan , Xiaojie Chen , Fuyan Zhang , Zehui Si , Xilong Zhao

{"title":"Analysis of acrylamide irradiation degradation effects and products in the starch mechanism","authors":"Long Cui , Mengyuan Zhang , Xian Wang , Jun Xi , Liping Cheng , Mingcheng Yang , Dong Zhang , Huili Yan , Xiaojie Chen , Fuyan Zhang , Zehui Si , Xilong Zhao","doi":"10.1016/j.apradiso.2025.111860","DOIUrl":"10.1016/j.apradiso.2025.111860","url":null,"abstract":"<div><div>Acrylamide (AA), a neurotoxic and potentially carcinogenic compound, forms in starch-rich foods during high-temperature processing, raising significant food safety concerns. Effective AA mitigation strategies are essential. Among degradation methods, irradiation is a promising food processing technology that reduces harmful contaminants without compromising food quality. To investigate the effect of irradiation on AA degradation and explore potential degradation mechanisms, this study first established a liquid chromatography-based detection method to detect AA in starch matrices. Starch matrices containing AA were irradiated with <sup>60</sup>Co-γ rays, and the effects of irradiation dose, initial concentration, and moisture content on degradation efficiency were analyzed. Furthermore, high-performance liquid chromatography-quadrupole time-of-flight mass spectrometry (HPLC-Q-TOF-MS) was employed to identify degradation products and elucidate their formation pathways. Results demonstrated that liquid chromatography effectively detected AA in starch matrices. At an initial AA concentration of 1000 mg/kg and 60 % moisture content, a 2 kGy irradiation dose achieved a 99.12 % degradation rate. Total ion chromatogram analysis identified 17 degradation compounds, with five key products primarily formed through graft polymerization reactions between AA and glucose in the starch matrix. In conclusion, optimized <sup>60</sup>Co-γ irradiation effectively degrades AA in starch-based food matrices while generating specific degradation products. These findings offer valuable insights into applying irradiation technology to reduce AA, providing an important reference for enhancing food safety control strategies.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111860"},"PeriodicalIF":1.6,"publicationDate":"2025-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143903738","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}

引用次数: 0

Combining 3D printing with OSL dosimeters for extremity monitoring according to ICRU 95 operational quantity 结合3D打印与OSL剂量仪，根据ICRU 95操作量进行肢体监测

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-22 DOI: 10.1016/j.apradiso.2025.111838

Gabriel H.R.B. França, Helen J. Khoury, Viviane K. Asfora, Vinícius S.M. de Barros

{"title":"Combining 3D printing with OSL dosimeters for extremity monitoring according to ICRU 95 operational quantity","authors":"Gabriel H.R.B. França, Helen J. Khoury, Viviane K. Asfora, Vinícius S.M. de Barros","doi":"10.1016/j.apradiso.2025.111838","DOIUrl":"10.1016/j.apradiso.2025.111838","url":null,"abstract":"<div><div>The International Commission on Radiation Units and Measurements (ICRU) has recently proposed on its Report 95 a new set of operational quantities for personal and area monitoring. The definition of such quantities is then greatly simplified by adopting the same phantoms already in use to calculate Protection quantities. However, the existing conversion coefficients between these kerma and the operational quantities changes, causing current personal dosimeters to be directly affected as well. Therefore, it is needed for dosimeters to evolve in order to handle changes in their energy dependence response, which often requires re-evaluations or even re-designing holders from sketch. In this scenario, the present paper aims to demonstrate the viability of combining 3D printing through stereolithography (SLA) technique with optically stimulated (OSL) technology of beryllium-oxide (BeO) commercial crystals in manufacturing a dosimeter holder to be used in wrist-type dosimeters for photons. Such dosimeter holder must be able to fulfil the current international criteria even for the new operational quantity proposed by ICRU 95. After being created and properly calibrated, the holder underwent energetic and angular assessment tests. The results showed that the badge performed within a relative response range of approximately <span><math><mrow><mo>±</mo><mn>20</mn><mtext>%</mtext></mrow></math></span>. These tests were conducted within an energy range of 23-662 keV and angles ranging from 0°to 60°, as outlined in IEC 62387:2020. The dosimeter demonstrated a satisfactory performance under the specified conditions set by the IEC standard.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111838"},"PeriodicalIF":1.6,"publicationDate":"2025-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868304","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}

引用次数: 0

Leveraging gamma and alpha spectrometry optimizes gross alpha measurements for miscellaneous radioactive waste 利用伽马和α光谱法优化了各种放射性废物的总α测量

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-21 DOI: 10.1016/j.apradiso.2025.111853

Tae-Hong Park , Kanghyun Yoo , Kyunghun Jung , Kwang-Soon Choi , Jung-Weon Choi , Gi Yong Kim , Hyeju Lee , Minyoung Jung , Jung Bo Yoo , Jai Il Park

{"title":"Leveraging gamma and alpha spectrometry optimizes gross alpha measurements for miscellaneous radioactive waste","authors":"Tae-Hong Park , Kanghyun Yoo , Kyunghun Jung , Kwang-Soon Choi , Jung-Weon Choi , Gi Yong Kim , Hyeju Lee , Minyoung Jung , Jung Bo Yoo , Jai Il Park","doi":"10.1016/j.apradiso.2025.111853","DOIUrl":"10.1016/j.apradiso.2025.111853","url":null,"abstract":"<div><div>Determination of alpha emitter concentration is crucial for ensuring safety and compliance in radioactive waste disposal. This study uses gamma and alpha spectrometry to optimize gross alpha measurements for radioactive waste by selecting appropriate calibration curves. The lack of a priori knowledge about the compositions of alpha emitters often results in discrepancies between the gross alpha activities and the summed activities of all alpha emitters when a single mass efficiency curve, such as based on <sup>241</sup>Am, is applied. We addressed this by revisiting gamma spectrometric data to categorize waste samples into uranium-major and the other groups, applying natural uranium calibration for the former and <sup>241</sup>Am calibration for the latter. This approach corrected the underestimated gross alpha activities of the uranium-major samples and derived a better correlation between gross alpha activities and alpha activity sums from the alpha spectrometry.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111853"},"PeriodicalIF":1.6,"publicationDate":"2025-04-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143878906","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}

引用次数: 0

Comparison of measurement techniques and sorption of radium-226 in low and high salinity aqueous samples 低、高含盐量样品中镭-226的测量技术及吸附比较

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-19 DOI: 10.1016/j.apradiso.2025.111851

Sarah E. Donaher , Jiusi Wang , Nicole E. Martinez , Brian A. Powell

{"title":"Comparison of measurement techniques and sorption of radium-226 in low and high salinity aqueous samples","authors":"Sarah E. Donaher , Jiusi Wang , Nicole E. Martinez , Brian A. Powell","doi":"10.1016/j.apradiso.2025.111851","DOIUrl":"10.1016/j.apradiso.2025.111851","url":null,"abstract":"<div><div>Human activities have the potential to redistribute radium (Ra) in the marine environment in a manner that may necessitate monitoring or management of subsequent human or environmental exposures. There is therefore a need to identify accurate and accessible techniques for Ra measurement in high salinity samples and to describe the distribution of Ra in estuarine and marine environments, but most efforts in these areas have focused on low salinity matrices. In addition, rapid and reliable measurements are crucial for time-sensitive samples such as short-lived isotopes or emergency situations. The objective of this study is to describe the limits of detection, cost, and relative ease for measurement of Ra in both low and high salinity aqueous samples via three analytical methods: liquid scintillation counting (LSC), high purity germanium (HPGe) gamma spectrometry, and inductively coupled plasma mass spectrometry (ICP-MS). To contextualize these measurements for real-world scenarios, the partitioning of <sup>226</sup>Ra to substrates relevant to the marine environment was also characterized. Although HPGe detection with solid phase extraction had the lowest limit of detection for low salinity samples (0.27 Bq L<sup>−1</sup>), poor <sup>226</sup>Ra recovery for high salinity samples and high materials costs make this method prohibitive for many users. Limits of detection for high salinity samples were lower for LSC (1.28 Bq L<sup>−1</sup>) than for ICP-MS without dilution (11.4 Bq L<sup>−1</sup>), but significant and unexpected degradation of the high salinity LSC standards was observed after six months. Therefore, our preferred measurement method for high salinity Ra samples is ICP-MS with sample dilution as necessary to reduce matrix effects.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111851"},"PeriodicalIF":1.6,"publicationDate":"2025-04-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868461","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}

引用次数: 0

Investigation of the chemical and structural composition of scale deposits in piping systems conveying thermal water from Ain Skhouna spring, Agadir region 阿加迪尔地区Ain Skhouna温泉热水输送管道系统中水垢沉积物的化学和结构组成的调查

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-18 DOI: 10.1016/j.apradiso.2025.111855

Sara Darbal , Ilham Karmal , Mustapha Nassiri , Said Ben-Aazza , M'barek Belattar , Abdelilah Fatni , Mohamed El Housse , Ali Driouiche

{"title":"Investigation of the chemical and structural composition of scale deposits in piping systems conveying thermal water from Ain Skhouna spring, Agadir region","authors":"Sara Darbal , Ilham Karmal , Mustapha Nassiri , Said Ben-Aazza , M'barek Belattar , Abdelilah Fatni , Mohamed El Housse , Ali Driouiche","doi":"10.1016/j.apradiso.2025.111855","DOIUrl":"10.1016/j.apradiso.2025.111855","url":null,"abstract":"<div><div>In order to solve the problem of scaling in the pipes used to transport thermal waters from the Ain Skhouna spring in the Agadir region, a physico-chemical analysis of the water and a complete characterization of the scale collected from these pipes are required. The aim of this study is to investigate the clogging of pipes carrying thermal water. Physico-chemical analyses of the water revealed high mineralization, a hardness of approximately 195 °F, and elevated concentrations of major ions, notably Ca<sup>2+</sup> and SO<sub>4</sub><sup>2−</sup>, which precipitate and cause clogging issues. The scale collected from inside the thermal water pipe was analyzed using various analytical techniques, including X-ray diffraction (XRD), X-ray fluorescence (XRF), thermogravimetric analysis (TGA), differential thermal analysis (TDA), Fourier transform infrared spectroscopy (FTIR), scanning electron microscopy (SEM), and energy-dispersive X-ray spectroscopy (EDS). Identification of the scale deposit using XRF revealed that the sample contained 47.3 % calcium oxide (CaO) and 45.5 % sulfur trioxide (SO<sub>3</sub>), corresponding to a calcium sulfate content of 92.8 %. The results of XRD and SEM, combined with EDS analysis, revealed that the scale sample consisted mainly of calcium sulfate dihydrate, with trace amounts of calcium carbonate. Thermal analysis indicated a 19.31 % mass loss, consistent with the dehydration of calcium sulfate dihydrate. This study provides insights into addressing the issue of calcium sulfate dihydrate clogging of thermal water pipes at the Ain Skhouna spring.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111855"},"PeriodicalIF":1.6,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143854806","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}

引用次数: 0

In situ electrochemical synthesis of copper-zinc ferrocyanide for removal of cesium in simulated liquid radioactive wastes 铜锌亚铁氰化物原位电化学合成去除模拟放射性液体废物中的铯

IF 1.6 3区工程技术

Applied Radiation and Isotopes Pub Date : 2025-04-18 DOI: 10.1016/j.apradiso.2025.111854

Wei Cao, Lanfang Hua, Huiqi Fan, Jie Fang, Guangtuan Huang

引用次数: 0