Applied Radiation and Isotopes最新文献

{"title":"Development and validation of a semi-automated [13N]Ammonia preparation system for clinical research","authors":"Victor Amador Diaz,&nbsp;Peter M. Hall ,&nbsp;Melissa J. Brown ,&nbsp;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>[¹³N]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 [¹³N]ammonia batches assessed against FDA standards for radiochemical purity, sterility, and quality.</div></div><div><h3>Results</h3><div>The module consistently delivered [¹³N]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 [¹³N]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}

{"title":"Combining 3D printing with OSL dosimeters for extremity monitoring according to ICRU 95 operational quantity","authors":"Gabriel H.R.B. França,&nbsp;Helen J. Khoury,&nbsp;Viviane K. Asfora,&nbsp;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}

{"title":"Comparison of measurement techniques and sorption of radium-226 in low and high salinity aqueous samples","authors":"Sarah E. Donaher ,&nbsp;Jiusi Wang ,&nbsp;Nicole E. Martinez ,&nbsp;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 ²²⁶Ra 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⁻¹), poor ²²⁶Ra 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⁻¹) than for ICP-MS without dilution (11.4 Bq L⁻¹), 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}

{"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 ,&nbsp;Ilham Karmal ,&nbsp;Mustapha Nassiri ,&nbsp;Said Ben-Aazza ,&nbsp;M'barek Belattar ,&nbsp;Abdelilah Fatni ,&nbsp;Mohamed El Housse ,&nbsp;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 Ca²⁺ and SO₄²⁻, 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 (SO₃), 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}

{"title":"In situ electrochemical synthesis of copper-zinc ferrocyanide for removal of cesium in simulated liquid radioactive wastes","authors":"Wei Cao,&nbsp;Lanfang Hua,&nbsp;Huiqi Fan,&nbsp;Jie Fang,&nbsp;Guangtuan Huang","doi":"10.1016/j.apradiso.2025.111854","DOIUrl":"10.1016/j.apradiso.2025.111854","url":null,"abstract":"<div><div>This study employed in situ electrochemical synthesis of copper-zinc ferrocyanide (CuZnFC) to effectively remove Cs⁺ from simulated liquid radioactive wastes (LRWs). Through single-factor experiments, the optimal reaction conditions were established as follows: an initial pH of 8.0, a molar ratio of [Fe(CN)₆]^4- to Cs⁺ of 10:1, a reaction temperature of 25 °C, a current density of 6 mA·cm⁻², and a stirring rate of 400 r·min⁻¹, achieving a Cs⁺ removal rate of 99.978 %. The precipitate analysis revealed its composition as CuZn[Fe(CN)₆]·6.18H₂O, which exhibited a cubic crystal structure and rapidly absorbed Cs⁺ from the simulated liquid radioactive wastes.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111854"},"PeriodicalIF":1.6,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143865214","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}

{"title":"Adsorption capacity and mechanism of uranium by Fusarium verticillioides HX-3 isolated from a uranium mining site","authors":"Qin Li ,&nbsp;Guangwen Feng ,&nbsp;Henglei Chen ,&nbsp;Changlong Cai ,&nbsp;Peihong Mao","doi":"10.1016/j.apradiso.2025.111857","DOIUrl":"10.1016/j.apradiso.2025.111857","url":null,"abstract":"<div><div>Microorganisms that survive in extreme environments may possess special survival abilities. In this study, the adsorption capacity and mechanism of <em>F. verticillioides</em> HX-3, a fungus isolated from uranium mine wastewater, for uranium were investigated. Single factor batch experiments such as adsorption time, biomass dosage, pH, temperature, initial uranium concentration and coexisting ion were used to study the uranium adsorption capacity of biomass. The adsorption mechanism was further explored using kinetic, isothermal, thermodynamic models, and microscopic characterization techniques. The results demonstrated that under optimal experimental conditions, the biomass reached an adsorption capacity of 10.47 mg/g at a uranium concentration of 15 mg/L, with an adsorption efficiencies of 93 %. The study also revealed that the biomass adsorption process involves inhomogeneous multilayer chemisorption and exhibits spontaneous endothermic behavior. SEM-EDS analysis revealed that U(IV) primarily adsorbs onto the biomass surface. FTIR analysis showed that the functions that played the main role in the adsorption process were amino, hydroxyl, carbonyl, and acylamino groups. In summary, <em>F. verticillioides</em> HX-3 holds great potential for treating uranium-containing wastewater and can serve as an environmentally friendly biosorbent.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111857"},"PeriodicalIF":1.6,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143854805","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}

{"title":"Sorption behavior of 137Cs and 60Co onto raw and cellulose-modified Greek bentonite","authors":"Dianellou Iro ,&nbsp;Noli Fotini ,&nbsp;Kantiranis Nikolaos","doi":"10.1016/j.apradiso.2025.111850","DOIUrl":"10.1016/j.apradiso.2025.111850","url":null,"abstract":"<div><div>Sorption properties of Greek bentonite from Kimolos in raw form and after cellulose-radiation modification were investigated for removal of cesium and cobalt from aqueous solutions. The sorption experiments were undertaken under different metal concentrations, without and with interfering ions, in single as well as in binary systems and the aqueous phase was analyzed through gamma ray-spectrometry using ¹³⁷Cs and ⁶⁰Co as tracers. Kinetic experiments revealed an ion exchange process. The structural and physicochemical changes after modification and metal sorption were examined through X-ray diffraction (XRD), Fourier transformed infrared spectroscopy (FTIR), scanning electron microscopy with energy dispersive X-ray spectroscopy (SEM-EDS), whereas the pH of point of zero charge (pH_pzc) and cation exchange capacity (CEC) were also determined. Sorption isotherms were reproduced through non-linear mathematical models, like the modified competitive Langmuir (MCL) and extended Freundlich (EF) models and their prediction accuracy was statistically tested through paired <em>t</em>-test at the 95 % confidence level. The results showed that both materials exhibited significant capacities (117 and 90 mg g⁻¹ the raw and modified bentonite for Cs, and 98 and 78 mg g⁻¹ for Co respectively). Both ions were found to have antagonistic behaviour in the binary system.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111850"},"PeriodicalIF":1.6,"publicationDate":"2025-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143865215","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}

{"title":"Densitometric measurement of 18O content of 18O-enriched water in relation to the production of 18F-labelled radiopharmaceuticals","authors":"Paula Y. Steinberg ,&nbsp;Franco T. Bietti ,&nbsp;Naila Gomez ,&nbsp;Guillermo Casale ,&nbsp;Horacio R. Corti","doi":"10.1016/j.apradiso.2025.111848","DOIUrl":"10.1016/j.apradiso.2025.111848","url":null,"abstract":"<div><div>The densities of mixtures of ordinary water and ¹⁸O enriched water have been measured all over the range of compositions, at temperatures between 293.15 and 313.15 K, using a vibrating-tube densitometer. From the error analysis of the density data in the ¹⁸O enriched water region (atom % ¹⁸O &gt; 95) we concluded that densitometry measurements with an accuracy of ±0.00002 g cm⁻³, provide a simple, precise and low-cost method to determine the ¹⁸O enrichment degree of recycled heavy oxygen water used to generate radiopharmaceuticals, such as [¹⁸F]fluoro-2-deoxy-D-glucose for the Positron-Emission Tomography (PET) scanning.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111848"},"PeriodicalIF":1.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868462","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}

{"title":"Assessment of the level of uranium in groundwater and the role of public water purifiers in mitigating the concentration- A study from the south-western part of Bengaluru, Karnataka, India","authors":"D.N. Deepika ,&nbsp;M.R. Ambika ,&nbsp;M.B. Karthik Kumar ,&nbsp;N. Karunakara ,&nbsp;Sanjeev Kimothi ,&nbsp;N. Nagaiah","doi":"10.1016/j.apradiso.2025.111849","DOIUrl":"10.1016/j.apradiso.2025.111849","url":null,"abstract":"<div><div>Groundwater samples were gathered from various sites adjacent to Manchanabele Reservoir and their uranium concentration was measured using a Light Emitting Diode (LED) fluorimeter. The results show that the uranium concentration varied widely from 0.2 to 358.1 ppb, with a Geometric Mean (GM) of 16.51 ppb. According to the Atomic Energy Regulatory Board (AERB) and World Health Organization (WHO) standard values, high uranium concentrations are found in 23 % and 34 % of samples, respectively. Water samples from public water purifiers which use reverse osmosis were also taken from the same locations in order to comprehend the potential decrease in uranium content. The uranium concentration in these samples varied from 0.2 to 18.1 ppb, with a GM of 0.32 ppb. Every water sample taken from the water purifiers reveals a concentration that is well within the safe limit of 30 ppb. Uranium levels are found to be comparatively very less in purified waters than those collected directly from the borewells. From the measured concentration of uranium, the radiological risk parameters estimated in terms of lifetime cancer risk is in the range of 0.001x10⁻³ to 1.14x10⁻³ with GM of 0.05x10⁻³. The chemical toxicity risk measured as lifetime annual daily dose is found to range from 0.007 to 13.34 μg/kg/day with GM of 0.61 μg/kg/day for groundwater samples and 0.0006x10⁻³ to 0.05x10⁻³ with GM of 0.001x10⁻³, 0.0074–0.67 μg/kg/day with GM of 0.012 μg/kg/day for purified water samples. Annual Effective Dose (AED) for the different age group was estimated and the values for Infants, children and Adults are found to vary between 0.4 and 734.99 μSv/y with a GM of 33.88 μSv/y, 0.141–251.84 μSv/y with a GM of 11.61μSv/y and 0.17–310.60μSv/y with a GM of 14.32 μSv/y for groundwater samples and 0.41–37.14 μSv/y with GM of 0.65 μSv/y, 0.14–12.72 μSv/y with GM of 0.22 μSv/y, 0.17–15.69 μSv/y with GM of 0.27 μSv/y respectively for purified water samples. The physicochemical parameters like pH and Total Dissolved Solids (TDS) were also measured and the dependence of uranium concentration on these parameters has also been studied.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111849"},"PeriodicalIF":1.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143852226","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}

{"title":"Potential risks of in-situ microbial remediation of uranium-contaminated groundwater: Uranium release and remigration","authors":"Wang Liu ,&nbsp;Junwen Lv ,&nbsp;Jinxi Peng ,&nbsp;Zeyu Li","doi":"10.1016/j.apradiso.2025.111847","DOIUrl":"10.1016/j.apradiso.2025.111847","url":null,"abstract":"<div><div>After in-situ microbial remediation of uranium-contaminated groundwater, the environmental problems caused by the remigration of uranium immobilized in the aquifer due to microbial decay require attention. In this study, uranium-containing <em>Leifsonia</em> sp. spoilage was produced by natural decay of uranium-adsorbed <em>Leifsonia</em> sp.<em>.</em> Batch experiments were used to investigate the influence on uranium release from the <em>Leifsonia</em> sp. spoilage under the conditions of different pH, action time, and concentrations of the metal ions K⁺, Ca²⁺, Na⁺, Mg²⁺, and Zn²⁺. The remigration of immobilized uranium was simulated by the <em>Leifsonia</em> sp. spoilage sand column experiment. The release rate of uranium initially decreased with increasing pH, increased with increasing contact time, and then remained unchanged with increasing time; the release rate of uranium peaked at 4.98 % at pH 3 and 120 h. Compared to the absence of metal ions, the release rate of uranium increased by &gt;10 % under the action of metal ions, in which Ca²⁺had the greatest effect, up to 18.4 %. Furthermore, U(IV) in the spoilage was oxidized to U(VI), resulting in uranium release, and uranium release was related to hydroxyl, carboxyl, amino, and amide groups in the spoilage. The release kinetics of uranium were consistent with those of the Elovich and double constant models, indicating that the release of uranium was a multifactorial integrated chemical desorption process. In addition, the remigrated uranium in groundwater had two components: some of the uranium was released from the spoilage and migrated independently as uranyl ions, and some was present in the spoilage and migrated with the spoilage, the amount of the former being much greater than that of the latter. This study provides a theoretical basis for the rational use of microbial in-situ remediation of uranium-contaminated groundwater by in-situ leaching of uranium.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111847"},"PeriodicalIF":1.6,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143854817","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}