Health physics最新文献

{"title":"Evaluation of Pediatric Radiation Doses during Chest, Abdomen, and Babygram X-ray Examination Using GATE Code.","authors":"Noureddine Elamri, Maroine Tahiri, Redouane El Baydaoui, Mounir Mkimel, Mustapha Bougteb","doi":"10.1097/HP.0000000000002143","DOIUrl":"https://doi.org/10.1097/HP.0000000000002143","url":null,"abstract":"<p><p>One of the main concerns of radiography procedures is to produce diagnostic image quality with dose reduction, specifically for pediatric patients. In the present study, Monte Carlo simulations using GATE (Geant Application for Tomography Emission) code, coupled with a 7-wk-old voxel female baby model from the GSF (German Research Center for Environment Health) were performed to investigate how dose in digital chest, abdomen, and both chest and abdomen (babygram) x-ray examinations vary with tube voltage (40-60 keV) at a fixed value of current-time product (4 mAs) using different collimation and a digital radiography system. Organ dose (mGy) and effective doses (mSv) of three routine digital radiography examinations, namely anterior-posterior (AP) chest, anterior-posterior (AP) abdomen, and anterior-posterior (AP) chest-abdomen, were estimated using the Monte Carlo simulation method, GATE code. Organ doses ranged from 0.01 to a maximum of 2.5 mGy, while effective doses ranged from 0.01 to 0.3 mSv. The results of the present paper show that the organ doses and effective doses for chest, abdomen, and babygram x ray with digital radiography highlight no change, while increasing voltage and values obtained are still very low compared to similar references.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":"131 5","pages":"496-504"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149080702","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigation of Multi-parameter Synchronous Detection Technology for Radioactive Aerosols in Spent Fuel Dissolution Process.","authors":"Yongzhen Xia, Runjie Di, Yongji Xie, Xin Wang","doi":"10.1097/HP.0000000000002141","DOIUrl":"10.1097/HP.0000000000002141","url":null,"abstract":"<p><p>Spent-fuel dissolution produces multi-nuclide, high-activity aerosols. Gross α/β CAMs are prone to interference and slow response, limiting timely dose assessment and alarms. We developed an integrated multiparameter synchronous detection system to simultaneously measure activity concentration, spectra, and particle size. The instrument integrates sampling and optical sizing (0.1-10 μm) with a silicon barrier (α), thin-window proportional (β), and 2 × 2 NaI (Tl) (γ) detectors. Signals are digitized (14-bit/100 MS s -1 ) for pulse-shape discrimination and 8,192-channel spectrometry. Performance followed ISO 11929/Currie. Standard sources and mixed-nuclide aerosols were used for calibration, linearity, response, and misclassification tests; stability was assessed over 720 h (50 L min -1 , 60 s integration). Detection efficiencies were 26.3% ( 241 Am α), 42.5% ( 90 Sr/ 90 Y β), and 31.2% ( 137 Cs γ). Minimum detectable activities were 8.5 × 10 -7 Bq cm -3 ( 241 Am), 9.2 × 10 -7 Bq cm -3 ( 239 Pu), and 3.1 × 10 -6 Bq cm -1 ( 90 Sr/ 90 Y). Dynamic tests gave T 90 = 17.5 s and T 95 = 22.3 s; α/β misclassification < 5%; linearity across five orders (R 2 = 0.9987). Compared with a representative CAM, spectral resolving power improved ≈5-fold and response time shortened 10-20 times. Energy and efficiency drift over 720 h were ≤±2% and ≤±3%. Multi-parameter acquisition reduces dose-assessment bias from nuclide misidentification and size assumptions and shortens alarm latency to < 30 s in high-background, multi-nuclide environments, supporting ALARA and process control during spent-fuel dissolution.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"482-495"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148678564","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Effective Dose Estimations for the Swiss Survey on Medical Radiation Exposure of the Population in 2023.","authors":"Eleni Theano Samara, Barbara Ott, Dorothea Dagassan-Berndt","doi":"10.1097/HP.0000000000002135","DOIUrl":"10.1097/HP.0000000000002135","url":null,"abstract":"<p><p>To estimate the annual population dose from medical examinations, the frequency of the examinations and the effective dose (E) for each examination needs to be estimated. In the last Swiss survey covering 2023, the dose per capita due to medical irradiation was estimated to be 1.7 mSv. In the framework of the 2023 survey, the E for x-rays' modalities were calculated using different methods (bibliographic review, data from a dose management system, data from older surveys, etc.). This work aims to present the methodology followed for the estimation of E for various modalities. E was estimated for approximately 60 radiological examinations and groups of examinations. The advantages and limitations for each method are discussed.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":"131 5","pages":"434-445"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC13608334/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149080629","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"New Tools for Threshold-linked Radiological Protection.","authors":"Bobby R Scott","doi":"10.1097/HP.0000000000002136","DOIUrl":"10.1097/HP.0000000000002136","url":null,"abstract":"<p><p>The current system of radiological protection (SRP) is based on the linear no-threshold (LNT) hypothesis for radiation-caused cancer and other forms of health detriment. Now there is overwhelming evidence of a dose-rate-dependent population threshold (abbreviated t) absorbed dose for cancer induction. Thus, the SRP needs to be updated to account for the threshold, and tools for doing so are provided in this article. These tools include the organ/tissue-T-related, threshold{t}-based, equivalent dose H {t} T (e.g., in sieverts), which is evaluated using the threshold-based radiation weighting factor wR,t . A second tool is the population equivalent dose threshold HT,t . When used in radiation exposure limitation, its value is assigned for a reference group, reference organ/tissue characteristics, and reference exposure scenario (high dose rate), so that the equivalent dose limit H {t} T,lim is expressed as H {t} T < H {t} T,lim ≤ HT,t (high dose rate). A third tool is the organ/tissue-specific exceedance equivalent dose \"ΔH{t}T= H{t}T- HT,t≥ 0 Sv,\" which is summed to get the total-body exceedance (TBEX). For many different radiation exposure scenarios, TBEX will be zero (Sv), unlike for the effective dose E . With an updated SRP based on a modern-science-related population threshold dose for radiation-caused health detriment, use of the LNT-based effective dose E and the as low as reasonably achievable principle would no longer be credible.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"505-508"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147283347","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Organ Dose Assessment in Radiological Central Venous Port Procedures: An Experimental Phantom-Based Study.","authors":"Mehmet Toptaş, Abdurrahman Tünay, Özlem Ateşal, Duygu Tunçman Kayaokay, Fahrettin Fatih Kesmezacar, Osman Günay, Songül Çavdar Karaçam, Didem Çolpan Öksüz, Mustafa Demir, Ghada Al Misned, H O Tekin","doi":"10.1097/HP.0000000000002138","DOIUrl":"10.1097/HP.0000000000002138","url":null,"abstract":"<p><p>This study aimed to quantitatively evaluate radiation doses delivered to radiosensitive thoracic and cervical organs during fluoroscopy-guided central venous port (CVP) catheter placement using a standardized experimental setup to identify the most exposed anatomical regions. An Alderson Rando anthropomorphic phantom equipped with calibrated MTS-100 thermoluminescent dosimeters (TLDs) was employed to simulate a typical CVP fluoroscopic procedure. The setup used a Siemens Artis Zee C-arm fluoroscopy system with a total active exposure time of 8 min, replicating clinical practice. Absorbed dose measurements were obtained from 14 organ sites, including lungs, thyroid, spinal cord, and upper airway structures. The highest radiation doses were observed in thoracic organs, with measured values of 7.84 ± 0.28 mGy for the right middle lung, 5.23 ± 0.40 mGy for the thoracic spinal cord, and 3.91 ± 1.47 mGy for the right lung apex. The thyroid received moderate exposure, recording 1.48 ± 0.35 mGy (right lobe) and 1.41 ± 0.68 mGy (left lobe). In contrast, distant organs such as the pituitary gland and ethmoid sinus exhibited negligible absorbed doses (< 0.03 mGy). Fluoroscopic CVP placement results in substantial localized radiation exposure, particularly to the lungs and thyroid. Quantitative organ dose mapping using an anthropomorphic phantom provides a valuable reference for optimizing patient safety protocols and minimizing radiation exposure during interventional procedures.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"461-467"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147283412","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Evaluation of Natural Radionuclides and Associated Health Risk Assessment in Soil and Rock Samples of Northeastern Rajasthan, India.","authors":"Sunil Kumar, Sandeep Kansal, Vikas Duggal, Bhupesh Khyalia","doi":"10.1097/HP.0000000000002132","DOIUrl":"10.1097/HP.0000000000002132","url":null,"abstract":"<p><p>The focus of this research is the measurement of terrestrial radionuclides ( 226 Ra, 232 Th, and 40 K) in 15 soil and 15 rock samples collected from Alwar district, Rajasthan, India. The NaI(Tl) scintillation spectrometry technique was implemented to determine radionuclide levels. The levels of terrestrial radionuclides in soil samples ranged from 9.50 to 40.64 Bq kg -1 for 226 Ra, 24.98 to 33.00 Bq kg -1 for 232 Th, and 224.61 to 332.77 Bq kg -1 for 40 K, having an arithmetic mean value 26.46, 28.44, and 275.90 Bq kg -1 , respectively, while in rock samples, its levels varied from 5.87 to 91.11 Bq kg -1 for 226 Ra, 18.32 to 37.81 Bq kg -1 for 232 Th, and 194.94 to 609.34 Bq kg -1 for 40 K, respectively, with an arithmetic mean value 22.47, 24.38, and 325.19 Bq kg -1 . The observed mean values of soil as well as rock samples were well below worldwide mean values of 32, 45, and 420 Bq kg -1 for 226 Ra, 232 Th, and 40 K, respectively, stated by the United Nations Scientific Committee on the Effects of Atomic Radiation. Radium equivalent activity in soil along with rock samples ranged from 68.57 to 104.66 Bq kg -1 and 55.87 to 177.38 Bq kg -1 , having a mean value of 88.42 and 82.38 Bq kg -1 , respectively, which is well below the recommended limit of 370 Bq kg -1 established by the Organization for Economic Cooperation and Development. Mean values of internal, external, gamma, and alpha indices were below unity, indicating negligible radiological risk from the soil as well as rock samples.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"414-423"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147283400","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Medical Exposure from Diagnostic Examinations and Procedures of the Swiss Population: 2023 Review.","authors":"Eleni Theano Samara, Barbara Ott, Reto Treier, Philipp R Trueb, Florentin Krämer, Tino Schönleitner, Achim Escher, Valerie Treyer, Thomas Krause, Dorothea Dagassan-Berndt, Elmar M Merkle","doi":"10.1097/HP.0000000000002133","DOIUrl":"10.1097/HP.0000000000002133","url":null,"abstract":"<p><p> This survey aimed to estimate the radiation exposure of the Swiss population from medical diagnostic procedures performed in 2023. The survey was based on billing data and administratively collected data for radiology and nuclear medicine and on data collection for the frequency of dental examinations. A total of 12.9 million radiological examinations were performed, corresponding to 1,443 examinations per 1,000 inhabitants. The collective effective dose was 1.69 mSv per capita, presenting a 13% increase compared with the dose estimated in 2018. Despite accounting for only 14.4% of the total number of examinations, computed tomography accounted for 75.7% of the total dose. In 2023, 207 CT scans per 1,000 inhabitants were recorded, with an average dose of 1.28 mSv per capita. The highest contribution to the examination frequency (46.5%) was recorded in dentistry, but this accounted for only 0.6% of the total dose (0.01 mSv per capita). The survey resulted in an update of the national data on population dose exposure from medical diagnostic procedures.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":"131 5","pages":"424-433"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC13608267/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149080682","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Determining the Biological Variability of Daily Amount of Feces to Estimate Dose Uncertainties Based on Data from Mayak Plutonium Workers.","authors":"Alexandra B Sokolova, Scott C Miller, Richard K Bull, Alexander V Efimov","doi":"10.1097/HP.0000000000002131","DOIUrl":"10.1097/HP.0000000000002131","url":null,"abstract":"<p><p>The most effective current methods to estimate internal radiation doses from exposures to plutonium containing compounds are based on measured nuclide activity in excreted urine and feces. Typically, urine measurements are made, but fecal measurements can provide additional information about the nature of the exposures. Interpreting and applying the results requires consideration of uncertainties associated with the measurements and subsequent calculations. There are large variations in the daily activities excreted in urine and feces. These uncertainties are characterized as Type A uncertainties (arising mainly from counting statistics) and Type B uncertainties (arising from a range of other error sources such as variation in excreted volumes or masses). For assessment of plutonium exposures, the overall uncertainties are described as \"scattering factors\" (SFs) obtained by combining these two types of uncertainty. The purpose of this study was to determine the daily fecal excretion volumes and associated SFs for 924 male and female plutonium workers at the Mayak Production Association, Ozersk, Russia. Excreta were measured during routine plutonium bioassays that were conducted in a clinical setting. Over 90% of the male and 80% of the female workers had lower daily fecal excretion masses than reported by the ICRP for reference man and reference woman. This may be at least partially due to the lower fiber content of the diet. The SFs calculated for individual cases were within the range of 1.0 to 3.0 in 84% of the cases with a geometric mean of 2.3 and range from 1.0 to 23.1. No statistical bias was found between the SF values between male and female workers.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"509-514"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147283333","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"How Important Is the FLASH Effect in a Nuclear Explosion?","authors":"Yvan Dutil, Ir Martin Benoît Gagnon","doi":"10.1097/HP.0000000000002139","DOIUrl":"10.1097/HP.0000000000002139","url":null,"abstract":"<p><p>A very high dose rate of ionizing radiation (> 40 Gy s -1 , \"FLASH\" radiation) causes less damage to healthy cells than moderate dose rates. Following a nuclear explosion, a significant fraction of the radiation dose is delivered at this rate. Consequently, there is a potential impact on the radiation risk estimates currently in use, which are largely based on the studies of the populations of Hiroshima and Nagasaki. Based on the scientific literature covering the relevant dose range, we estimate the maximum protective effect on genetic damage is about a factor 0.6 (-40%). Using this number and the relevant dosimetry for the Life Span Study population, while excluding data doses above 4 Gy, the maximum magnitude of the effect for Hiroshima would be somewhere between 3.3% and 13.1%, depending on the dose received. These values are sensitive to the neutron relative biological effectiveness (RBE), which was assumed to be 10 in the nominal case. In Nagasaki, the magnitude varies little with the dose, between 7.3% and 9.3%, and is relatively insensitive to the neutron RBE. Nevertheless, there are some indications that a threshold for this effect around 1 Gy may be observed in biodosimetric studies of this population. Still, due to the high heterogeneity in the relevant experimental data, further research should be carried out to investigate the FLASH effect at doses relevant to epidemiology (between 0.1 to 4 Gy) instead of the higher doses used in radiotherapy, for which most research on FLASH effect is carried out.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"515-521"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147377180","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Dissolution Behavior of Uranium Aerosols in Simulated Lung Fluids: Effects of Particle Size.","authors":"Ibtisam Yusuf, Edvin Hansson, Mats Eriksson, Mårten Dario, Håkan B L Pettersson","doi":"10.1097/HP.0000000000002137","DOIUrl":"10.1097/HP.0000000000002137","url":null,"abstract":"&lt;p&gt;&lt;p&gt;As uranium is a health hazard for nuclear fuel workers, correct dose assessments are necessary to ensure worker safety. Absorption parameters of uranium aerosols are important parameters for the dose assessments. In this study, size-fractionated uranium aerosols of uranium hexafluoride (UF 6 ), ammonium uranyl carbonate (AUC), uranium dioxide (UO 2 ), and uranium octoxide (U 3 O 8 ) collected from four workshops at a nuclear fuel fabrication plant were used in two separate in vitro dissolution models, one with simulated lung-lining fluid (Gamble's fluid) and one with simulated phagolysosomal fluid (PSF). The dissolution characteristics in the different simulated lung environments were assessed. Lung absorption parameters: the rapid fraction (f r ), rapid rate (s r , d -1 ), and slow rate (s s , d -1 ) were derived, and the dosimetric impact was evaluated. The conversion workshop has a known presence of uranium aerosols of both soluble (UF 6 , AUC) and relatively insoluble (UO 2 ) compounds. Absorption parameters derived for dissolution in Gamble's fluid in comparison to dissolution in PSF showed a mixed pattern with impactor stages. Absorption parameters fr , sr , and ss were generally slightly lower in PSF. However, a higher slow rate in comparison to Gamble's fluid was derived in PSF for some impactor cut-points, indicative of the different solubilities of the mixed aerosols. The fr,sr , and ss derived in PSF ranged between 0.1-0.3, 4-16 d -1 , and 0.004-0.015 d -1 , respectively. At the powder preparations and pelletizing workshops, less soluble uranium aerosols UO 2 and U 3 O 8 , are present. The absorption parameters derived for the pelletizing workshop from PSF were fr : 0.02-0.025, sr :4-6 d -1 , and ss : 0.0007-0.001 d -1 . For the powder preparations workshops, the fr ranged between 0.01-0.045, sr ranged between 4-32 d -1 , and ss ranged between 0.002-0.004 d -1 . The slow rates derived in PSF were several times higher than for Gamble's fluid, which resulted in ss : 0.00009-0.0004 d -1 and ss : 0.0001-0.001 d -1 for powder preparations and pelletizing workshops, respectively. The slow rate derived from dissolution in PSF showed good agreement with available in vivo data from studies performed at the pelletizing workshop. For the BA pelletizing workshop with UO 2 and U 3 O 8 aerosols that are blended with Gd 2 O 3 , fr , sr , and ss ranged between, 0.05-0.1, 1-7 d -1 and 0.002-0.005 d -1 , respectively. No substantial differences in derived parameters for dissolution in PSF or Gamble's fluid were visible. The difference between dissolution patterns in the two fluids between aerosols from the BA pelletizing and from the other two workshops are believed to be related to differences in the specific surface area (SSA), differences in the mixture of uranium compounds, and the blending with Gd 2 O 3 . No significant correlation between absorption parameters and impactor stages was found in any of the solutions for the four workshops, with","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"446-460"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC13608279/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147365008","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}