Health physics最新文献

{"title":"The Radiopharmaceutical Industry in Morocco: An Analytical Overview of Constraints and Developmental Prospects.","authors":"Hasnae Guerrouj, Ayat Mouaden, Mustapha Bouatia, Majdouline Bel Lakhdar","doi":"10.1097/HP.0000000000002080","DOIUrl":"10.1097/HP.0000000000002080","url":null,"abstract":"<p><p>The Moroccan radiopharmaceutical industry is currently under development. The country has two operational cyclotrons capable of producing fluorine-18-labeled radiopharmaceuticals (RPs), primarily for PET imaging, while all other therapeutic and SPECT-dedicated RPs are imported. Importation processes are administratively complex and subject to fluctuations in global supply chains. The RP industry also faces additional challenges, including a stringent regulatory framework, limited accessibility, reimbursement barriers, and a scarcity of trained professionals in radiopharmacy and nuclear medicine more broadly. Furthermore, limited education and awareness among referring clinicians hinder the integration of some nuclear medicine procedures into routine clinical practice. Despite these challenges, Morocco has significant potential for localized RP production. Strategic investment and partnerships with key international agencies could enhance radiopharmacy infrastructure, streamline regulatory pathways for local manufacturing, and foster the development of new training programs for professionals in Morocco and other African countries.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"155-163"},"PeriodicalIF":1.2,"publicationDate":"2026-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146105001","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 and Health Status Analysis of Radon Exposure in Different Underground Nonuranium Mines: Effect of Mining Technology on Radon Release.","authors":"Gang Liu, Rong Zhang, Yin Yin Liu, Ye Li, Qin Xiao Wu, Hong Xiao Xu, Xue Zhang, Yu Ming Zhang","doi":"10.1097/HP.0000000000002083","DOIUrl":"10.1097/HP.0000000000002083","url":null,"abstract":"<p><p>Long-term exposure to high concentrations of radon has been identified as an important risk factor for lung cancer. The risk of radon exposure in nonuranium mines has been ignored for a long time because of insufficient protective measures and weak health awareness among practitioners. To understand the effects of radon exposure on human health in the microenvironments of underground nonuranium mines and to explore the effects of cumulative radon exposure on the health of miners. The National Occupational Radiation Sickness Surveillance Workbook (Survey of Miners with High Radon Exposure) and an expert consensus on low-dose spiral CT screening for lung cancer were used. A total of 62 miners were selected from underground nonuranium mines. Chromosome aberrations in peripheral blood lymphocytes, micronuclei in lymphocytes, and low-dose CT screening of lung cancer were used as observation indices. There are significant differences in the detection rates of Nodular shadows and Patches and cable strip shadows in miners between an iron ore mines, gold mines and miners in deep nonuranium mines.Combined with monitoring data from nonuranium mines in iron and gold mines, this study reveals that the occupational health status of workers in underground nonuranium mines is at risk of lung cancer caused by radon exposure, and improving mining technology to reduce the deposition of radon and its progeny is the key.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"164-172"},"PeriodicalIF":1.2,"publicationDate":"2026-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147325794","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":"Breaking the LNT Code: The First Detailed Evaluation of the Unpublished Technical Reports by the BEAR I Genetics Panel Used to Support Their Linearity Decision.","authors":"Edward J Calabrese, Paul B Selby","doi":"10.1097/HP.0000000000002088","DOIUrl":"10.1097/HP.0000000000002088","url":null,"abstract":"<p><p>The 1956 recommendation by the US National Academy of Sciences (NAS) Biological Effects of Atomic Radiation (BEAR) I Genetics Panel to transition from a threshold to a linear dose response model for hereditary effects had a profound impact on environmental/occupational risk assessment, affecting policies/practices of US regulatory agencies, having much influence on regulations worldwide to the present. The recommendation gained influence due to the authority of the NAS, the prestige of the Panel, and the claim of a striking degree of uniformity among six independent estimates of radiation-induced hereditary risk. This claim was orchestrated by panelist James Crow who removed conflicting findings from the nine panelists who submitted estimates, acting with the approval of the entire Panel. These misrepresentations were ensured by the US NAS President who refused to share the Panel's technical reports and related documents with the scientific community. Ironically, the mouse mutation rate data used by the panelists who calculated risk estimates for either mouse or Drosophila were incorrect due to falsification by panelist William Russell without their knowledge. This action led to greatly exaggerated mutation risks and enhanced their overall false impression of agreement/scientific convergence. The actions of Crow were such that the already grossly inflated and falsified risk estimates of the panelists were made to appear in reasonably good agreement. These massive and compounded errors and deceptions have significantly affected regulatory practices for cancer risk assessment in the US and globally to the present. The present paper provides for the first time in the scientific literature an assessment of the unpublished technical reports of each of the nine participating geneticists of the BEAR I Genetics Panel and provides the basis for the above critical conclusions.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"233-251"},"PeriodicalIF":1.2,"publicationDate":"2026-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146149638","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":"Differences in Radiological Risk Perceptions Following Online and In-Person Workshops.","authors":"Victoria B Strait, Robert H Hayes, Mohammad G Mostofa","doi":"10.1097/HP.0000000000002201","DOIUrl":"https://doi.org/10.1097/HP.0000000000002201","url":null,"abstract":"<p><p>Nuclear energy is widely regarded as a critical part of the pathway toward a secure, low-carbon electricity grid, yet long-term management of used nuclear fuel remains a persistent challenge. Although technically viable options for interim and consolidated storage exist, public concern and community opposition - rooted in historical distrust and risk perception - continue to complicate siting decisions. In response, recent federal efforts have emphasized collaboration-based approaches and community engagement, though empirical evidence on the effectiveness of different engagement strategies remains limited. This study examines how the structure and delivery of community engagement influence changes in public attitudes toward hosting interim used nuclear fuel storage facilities. Using survey data from 13 educational workshops around the United States, we evaluate: (1) the inclusion of trust-building content prior to technical content, and (2) engagement format, comparing online and in-person workshops. Analyses focus on participant changes in perceptions of safety, risk, and support for hosting, using the Wilcoxon rank-sum test and other non-parametric hypothesis tests on surveys conducted before and after workshops. Results indicate that workshop participation is associated with some measurable attitude changes, with significant (p < 0.05) differences in response variability for some questions across workshop formats. In particular, when comparing nuclear energy to other clean energy sources, in-person workshop participants are substantially more likely to gain a more favorable opinion of nuclear energy than online participants. These findings contribute empirical evidence on how trust-building and delivery mode shape outcomes in public engagement on complex and contested energy policy issues such as storage of used nuclear fuel.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148873916","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":"Toward Indication-Stratified Local Reference Levels for IGRT Cone-Beam CT: A Clinical Audit of CTDIvol and DLP Across Ten Workflows on Versa HD.","authors":"O El Mouden, H Sekkat, A Bannan, F Chaara, H Bendouro, R El Baydaoui, M Bougteb, M Tahiri, O El Rhazouani, Y Berrada, M Mkimel","doi":"10.1097/HP.0000000000002204","DOIUrl":"https://doi.org/10.1097/HP.0000000000002204","url":null,"abstract":"<p><p>To characterize routine kV cone-beam CT (CBCT) imaging dose in image-guided radiotherapy (IGRT) and to derive indication-specific local benchmark values using and DLP for clinical protocol optimization. This retrospective single-center audit included 300 CBCT examinations acquired on a Versa HD linear accelerator (Elekta AB, Stockholm, Sweden) using XVI v5.0.4. Examinations were grouped into 10 clinical indication workflows. For each CBCT, acquisition descriptors (CTDI phantom, kVp, total mAs, scan arc, FOV, bowtie, scan length) and dose indices were extracted. (mGy) was analyzed as recorded (reference value). DLP (mGy cm-1) was derived/verified as × scan length. Indication-stratified distributions were summarized using mean ± SD and 95% CI, with examination-level visualisation. An optional parameter-based estimation model () was evaluated as a quality-control layer using Bland-Altman analysis. Across all examinations, was 3.25 ± 3.06 mGy (range 0.123-10.109) with median 1.44 mGy (IQR 0.84-5.96). DLP was 80.27 ± 75.66 mGy cm-1 (range 2.21-255.81) with median 34.36 mGy cm-1 (IQR 18.55-150.38). Dose indices differed markedly by indication (≈49-fold between lowest and highest mean ). The highest mean occurred for Prostate IGRT (7.69 ± 1.95 mGy) and Pelvic nodes (7.21 ± 1.83 mGy), whereas Extremity setup (0.156 ± 0.027 mGy) and Brain SRS/SRT (0.263 ± 0.062 mGy) were the lowest. DLP was highest for Pelvic nodes (187.6 ± 47.5 mGy cm-1) and Prostate IGRT (169.1 ± 42.9 mGy cm-1). The estimation model showed minimal bias (Bland-Altman bias 0.007 mGy; 95% limits of agreement -0.321 to 0.335 mGy). Routine IGRT CBCT dose on Versa HD/XVI shows strong indication dependence, driven by protocol selection and scan extent. The reported indication-resolved /DLP distributions provide a practical basis for local reference levels and targeted optimization of high-dose workflows (pelvic/abdominal) while preserving low-dose protocols for cranial/extremity indications.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148873882","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":"Proposal to Ensure Timely Resolution of Special Exposure Cohort Petitions.","authors":"Mike Mahathy","doi":"10.1097/HP.0000000000002150","DOIUrl":"10.1097/HP.0000000000002150","url":null,"abstract":"<p><p>The Energy Employees Occupational Illness Compensation Program Act of 2000 (EEOICPA) established a framework for compensating US Department of Energy (US DOE) workers and their survivors for illnesses resulting from exposure to radiation and toxic substances. Central to this framework is the Special Exposure Cohort (SEC) Rule, which enables compensation for groups of workers when dose reconstruction is infeasible. Since 2005, over 275 SEC petitions have been evaluated, resulting in 132 SEC classes at 83 sites. The evaluation process, managed by the National Institute for Occupational Safety and Health (NIOSH) and overseen by the Presidential Advisory Board Radiation and Worker Health (Advisory Board), is intended to be completed in a timely manner, but often extends for years, especially for petitions initially denied. The Savannah River Site petition exemplifies these delays, remaining unresolved after 18 y. This document reviews the SEC petition process, highlights delays, and proposes two options for reform: (1) instituting a 6-y limit for petition evaluation, after which unresolved cases are decided by the Secretary of Health and Human Services; and (2) legislative establishment of SEC classes for all workers at major US DOE sites through 28 February 1992 with subsequent classes reviewed under current procedures. The two options proposed herein aim to ensure timely resolution and uphold Congressional intent for efficient compensation.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"252-254"},"PeriodicalIF":1.2,"publicationDate":"2026-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148156358","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":"Single-Center, Open-Label, Randomized Controlled Trial on the Reduction of Scattered Radiation Exposure to the Primary Operator in Radial, Femoral, and Pectoral Cath Lab Procedures Using a Radiation Protection Drape.","authors":"Shodhan R Aithal, Hermohander Singh Isser, Zubair Farooq, Sandeep Bansal, Puneet Gupta","doi":"10.1097/HP.0000000000002100","DOIUrl":"10.1097/HP.0000000000002100","url":null,"abstract":"<p><p>Radiation exposure in the catheterization laboratory poses a significant occupational hazard for primary operators. This single-center, open-label, randomized controlled trial conducted at Vardhman Mahavir Medical College and Safdarjung Hospital, New Delhi, evaluated scattered radiation exposure to the primary operator during procedures via radial, femoral, and pectoral vascular access sites and the effectiveness of radiation protection drapes in reducing this exposure. A total of 216 patients (72 in each vascular access group) were randomized using coin flipping to receive either standard radiation protection or additional shielding with a radiation protection drape. The primary operator's scattered radiation dose was assessed in comparison to the radiation emitted during the procedure, with normalization to procedural radiation parameters including air kerma (AK), dose area product (DAP), and cine-adjusted screen time (CAST). Pectoral access was associated with the highest operator exposure (96.75 µSv) compared to femoral (45.72 µSv) and radial (49.06 µSv) access, despite lower AK values. Radiation protection drapes significantly reduced operator exposure across all access sites, with radial access showing reductions of 51% (DAP), 48% (AK), and 53% (CAST); femoral access showing reductions of 82% (DAP), 74% (AK), and 63% (CAST); and pectoral access showing reductions of 62% (DAP), 49% (AK), and 52% (CAST), all statistically significant (P < 0.05). No adverse events were reported. The findings provide strong support for the routine use of radiation protection drapes to minimize primary operator radiation exposure during catheterization procedures, especially when using the pectoral access site.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"201-209"},"PeriodicalIF":1.2,"publicationDate":"2026-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146104770","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":"Mapping Indoor and Outdoor Environmental Radiation Exposure at a Nigerian Tertiary Institution: Evidence from Federal College of Education, Gombe, Gombe State. Nigeria.","authors":"Muhammad Nuruddeen Abdulkareem, Isa Sabo Muhammad, Ibrahim Olanrewaju Abiodun, Muhammad Mudassir Usman, Mohammad Abubakar, Abdullahi Muhammad, Ahmad Alhassan, Mohammed Shettima Nur","doi":"10.1097/HP.0000000000002212","DOIUrl":"https://doi.org/10.1097/HP.0000000000002212","url":null,"abstract":"<p><p>Natural background ionizing radiation from terrestrial and cosmic sources results in continuous exposure of the population, particularly in educational environments where staff and students spend prolonged periods indoors and outdoors. Monitoring ambient gamma radiation and associated health risks is therefore essential for ensuring radiological safety and regulatory compliance. This study assesses background gamma radiation levels and corresponding radiological risk indices within the Federal College of Education (Technical), Gombe, Gombe State, Nigeria. Indoor and outdoor ambient gamma dose rates were measured at selected campus locations using a calibrated Radiation Alert Inspector Geiger-Muller detector. Measurements were conducted at a height of 1 m above ground level in accordance with UNSCEAR guidelines, with geographic coordinates recorded using a GPS receiver. Absorbed dose rate (ADR), annual effective dose equivalent (AEDE), and excess lifetime cancer risk (ELCR) were calculated using standard conversion factors and appropriate occupancy coefficients. Descriptive statistics were applied to evaluate spatial variability and compare results with international recommended reference levels. Indoor absorbed dose rates ranged from 15.00 to 46.67 nGy h-1, while outdoor values ranged from 15.00 to 40.00 nGy h-1. The mean indoor AEDE (0.227 mSv y-1) was higher than the outdoor mean (0.049 mSv y-1), primarily due to differences in occupancy factors. All estimated AEDE and ELCR values remained below the ICRP-recommended reference level of 1 mSv y-1 for public exposure, with spatial analysis revealing localized variability but no abnormal radiation hotspots. The findings indicate that ambient gamma radiation levels within the campus are within global background ranges and pose no significant radiological health risk. Regular monitoring is recommended to ensure sustained radiological safety in educational environments.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148818386","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 Torlon Containers for Minimizing Radiation Exposure During Medical Isotope Production in a Research Reactor.","authors":"Donald Nolting, Tristan Brannon, Rodrigo Viveros Duran, Joseph Lapka, Tracy Tipping, Mark Andrews, William Charlton","doi":"10.1097/HP.0000000000002197","DOIUrl":"https://doi.org/10.1097/HP.0000000000002197","url":null,"abstract":"<p><p>The production of medical isotopes in research reactors often involves handling highly radioactive samples and containers, which poses a radiation exposure risk to personnel. This study evaluates the performance of Torlon 4203 polyamide-imide (PAI) containers as an alternative to traditional aluminum containers used in the central thimble (CT) experimental facility of The University of Texas at Austin (UT-Austin) Nuclear Engineering Teaching Laboratory (NETL) TRIGA Mark II reactor. Four irradiation experiments compared aluminum and Torlon containers with lead and graphite ballast configurations. Gamma and beta dose rates were measured after irradiation at multiple distances. Torlon containers demonstrated more than a 13-fold reduction in gamma dose rates relative to aluminum 15 hours after irradiation, maintained structural integrity for more than 150 hours of irradiation over multiple experiments, and provided a water-tight seal. These findings suggest that Torlon containers can substantially improve radiation safety and operational efficiency in isotope production settings.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148818399","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":"Measurements of 177mLu contaminants in Lutetium-Based Therapeutics.","authors":"D Coll Segarra, S Arias Soriano, S V Tipnis, J A Nye","doi":"10.1097/HP.0000000000002205","DOIUrl":"https://doi.org/10.1097/HP.0000000000002205","url":null,"abstract":"<p><strong>Introduction: </strong>A practical approach is presented to reliably detect and quantify the long-lived contaminant 177mLu commonly found in 177Lu-based therapeutics.</p><p><strong>Objective: </strong>The objective of this work was to provide methods to measure 177mLu on detector systems typically found in hospital environments that support theranostic programs.</p><p><strong>Methods: </strong>Twenty-four samples (14 177Lu dotatate, 10 177Lu PSMA) were collected from unused patient vials. 1-mL aliquots were drawn from each vial for counting on a well-type, one-inch (2.5-cm) NaI detector and liquid scintillation counter (LSC) system that support the hospital theragnostic and radiation safety programs, respectively. Prior to measurement, all samples were counted on a well-type high-purity germanium detector (HPGe) to establish a quantification standard for comparison. All detectors were calibrated with known standards and counting durations were adjusted to achieve <5% error in the integrated photopeaks and beta spectra. Data were reported as percent ratio of 177mLu/177Lu.</p><p><strong>Results: </strong>The closely spaced photopeaks at 108 keV, 113 keV, and 122 keV were resolvable as a single peak on the NaI detector. For all 177Lu dotatate samples, the mean 177mLu/177Lu ratio was 6.22 × 10-3 +/- 1.32 × 10-3 % on the NaI well, which agreed with HPGe well at 5.86 × 10-3 +/- 1.73 × 10-3 %. The 177mLu/177Lu ratio from the LSC was higher at 8.49 × 10-3 +/- 1.96 × 10-3 % due to contributions from multiple beta decay transitions that could not be resolved. For all 177Lu PSMA samples, the mean 177mLu/177Lu ratio was four orders of magnitude lower than 177Lu dotatate with no observable photopeaks on the HPGe or NaI well detectors. Similarly the ratio from LSC measurements on 177Lu PSMA were at least three orders of magnitude lower than 177Lu dotatate.</p><p><strong>Conclusion: </strong>This work demonstrated that, some but not all, 177Lu-based therapeutics contain measurable amounts of 177mLu and the presence of this contaminant depends on the radioisotope production method. Spectroscopy methods using well-type and liquid scintillation systems can detect 177mLu but the liquid scintillation system could not quantify the total amount due to its inability to separate beta decay events from 177mLu and 177Lu decay. None of the measurements made with the well-type detectors on samples from 177Lu PSMA exceeded the minimum detectable activity for 177mLu.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148827117","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}