Journal of Radiological Protection最新文献

{"title":"Operational challenges of positive pressure systems for radiation protection in medical facilities.","authors":"Chihiro Matsumoto, Shota Tanabe, Chika Yamamoto, Tianchen Zhao, Toyoaki Sawano, Saori Nonaka, Hideyuki Kato, Fumie Yamaguchi, Shogo Takahara, Tomoaki Tanaka, Masaharu Tsubokura","doi":"10.1088/1361-6498/ae80d3","DOIUrl":"10.1088/1361-6498/ae80d3","url":null,"abstract":"<p><p>During nuclear disasters, shelter-in-place (SIP) is often a safer alternative to evacuation for patients in medical facilities who may be particularly vulnerable. In Japan, medical institutions located near nuclear facilities have been equipped with positive-pressure systems (PPS), designed specifically for radiation protection. However, operational protocols to execute and manage SIP and PPS remain poorly defined. This study aimed to investigate the challenges in implementing SIP at the time of nuclear catastrophe while maintaining essential clinical functions. A case study was conducted at the Matsue Red Cross Hospital, located within an urgent protective action planning zone. Data were gathered through participation in the hospital's nuclear disaster countermeasures committee and through analysis of meeting minutes, facility documents, and technical specifications. The findings revealed a fundamental conflict between the technical requirements of PPS and the continuity of clinical services. Four critical sub-challenges were identified: (1) the unavoidable presence of certain staff and patients in non-protected zones within the hospital; (2) the potential inability to maintain sufficient positive pressure in protected zones during active clinical service; (3) the difficulty in regulating indoor temperature and humidity as a consequence of PPS operation; and (4) the increased risk of external radiation exposure in the vicinity of PPS units when outdoor ambient dose rates are elevated. For facilities that already have PPS installed, further investigations into PPS operations and the development of countermeasures are necessary. Furthermore, when installing PPS in the future, it is desirable for the government, hospitals, and installation companies to thoroughly discuss operations and design systems to minimise the impact on hospital functions.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148310278","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Establishing a representative dose rate constant for ambient dose equivalent of Iodine-131: a first step toward patient body attenuation studies.","authors":"E Cortez, B M Mendes, T C F Fonseca, L Paixão","doi":"10.1088/1361-6498/ae80d4","DOIUrl":"10.1088/1361-6498/ae80d4","url":null,"abstract":"<p><p>This work establishes a representative ambient dose equivalent rate constant (Γ_{<i>H</i>*(10)}) for I-131 as a first step toward patient body-attenuation studies. Monte Carlo simulations with the EGSnrc code were used to evaluate Γ_{<i>H</i>(*10)}for point sources and the ICRU sphere, employing two photon-spectra datasets (RADAR and ICRP 107) and two scoring methods (fluence and air-kerma scoring). Simulations considered only photons above 20 keV, omitted electron transport, and achieved statistical uncertainties ⩽5%. Our results were consistent across spectra and geometries, yielding a representative mean Γ_{<i>H</i>*(10)}value of 63.6 ± 0.1<i>µ</i>Sv m² GBq^-¹ h^-¹. Comparison with published Γ_{<i>H</i>*(10)}values for I-131 showed differences ranging from -17% to +22% and close agreement with recent values and the literature average value. An adult male voxel phantom with biodistributed I-131 was then simulated to obtain the body ambient dose equivalent rate constant (Γ_{<i>H</i>*(10),body}) and a corresponding body attenuation factor (BAF) of 0.729 ± 0.002 at 1 m was estimated. As complementary validation, F-18 (511 keV photons) with FDG biodistribution produced a BAF of 0.628 ± 0.002 in the model used in this work. This value agrees with the literature. The proposed representative Γ_{<i>H</i>*(10)}reduces uncertainty in BAF estimates and can improve shielding calculations and dose assessments for caregivers and family members of patients undergoing I-131 therapy.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148310257","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Stochastic expansion of radionuclide inhalation dosimetry for consequence management application: uncertainty and sensitivity analysis in the ICRP 130 human respiratory tract model.","authors":"Emmanuel Matey Mate-Kole, Sara C Howard, Ashley P Golden, David A Hooper, Brandon A Wilson, Shaheen Azim Dewji","doi":"10.1088/1361-6498/ae81be","DOIUrl":"10.1088/1361-6498/ae81be","url":null,"abstract":"<p><p>Releases from nuclear or radiological security events can result in significant internal radiation contamination through inhalation of particulate contaminants. The reference human respiratory tract model (HRTM), developed by the International Commission on Radiological Protection (ICRP) and described in the ICRP Publication 66 with subsequent updates in the ICRP Publication 130, is used to evaluate the deposition and clearance behaviour of inhaled radionuclides. Biokinetic models are used to quantify the retention and excretion of internally deposited particulates, supporting the calculation of inhalation dose coefficients (DCs). The HRTM developed by the ICRP utilises deterministic quantities outlined in the ICRP Publication 66 and 130. The overarching goal of this study was to determine the variability from deterministic biokinetic/dosimetry models to represent the stochastic breadth of radionuclide metabolism in an exposed occupational population from realistic source terms, yielding an expanded compendium of inhalation DCs. The analysis was carried out in three phases: (1) Implementation and extension of the biokinetic and DC modelling framework based on the ICRP Publication 130 HRTM and associated element specific systemic biokinetic models; (2) Investigation of uncertain parameters in the HRTM; and (3) Stochastic analysis using Latin hypercube sampling, incorporating non-parametric (Kolmogorov-Smirnov statistics) test and quantile-quantile plot assessment to support parametric distribution selection, for characterisation of the committed effective DCs distributions. To determine the most impactful parameters among the uncertain parameters, a random forest regression model was employed for feature importance, coupled with SHapley Additive exPlanations for comprehensive machine learning interpretation of the features. This study presents a unique stochastic framework for modelling inhaled particulate metabolism, enhancing capabilities in radiation consequence management, medical countermeasure development, and radiation dose reconstruction for epidemiological investigations.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC13365721/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148320193","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Occupational radiation exposure in spine surgery: organ-specific OSL phantom dosimetry and workload-based risk assessment.","authors":"O Warimezgane, M Hilal, M R Mesradi, A Elanique, Y Aguezzoumen, A Saadi, M R Abbari, A Hadaoui","doi":"10.1088/1361-6498/ae8551","DOIUrl":"10.1088/1361-6498/ae8551","url":null,"abstract":"<p><p>Occupational radiation exposure during fluoroscopy-guided dorsolumbar spine surgery was evaluated using ATOM phantoms and carbon-doped aluminium oxide () nanoDot optically stimulated luminescence (OSL) dosemeters. A controlled 50-acquisition protocol (comprising anteroposterior, oblique, and lateral projections) was used to map organ-specific doses for an operating surgeon at 50 cm from the C-arm isocentre. The expanded measurement uncertainty was 7.6% (). In the unprotected configuration, the highest equivalent doses occurred in the thoracic region, specifically the breasts (0.0430 mSv/procedure), oesophagus (0.0335 mSv/procedure), lungs (0.0230 mSv/procedure), and stomach (0.0280 mSv/procedure). Standard protective equipment (0.5 mm Pb-equivalent) reduced these organ doses by 27.3%-42.9%. However, these reduction factors characterise the complete geometric setup rather than the intrinsic attenuation of individual shielding devices. Based on International Commission on Radiological Protection Publication 103 tissue-weighting factors, the calculated effective dose was 0.152 mSv per simulated procedure. Illustrative workload extrapolations () yielded cumulative annual effective doses of 14.58 mSv yrfor 96 procedures and 36.45 mSv yrfor 240 procedures. These scenario-based projections are highly specific to the evaluated setup, table height, and acquisition parameters. The findings support the utility of local kerma-area product-normalised dose audits, rigorous individual monitoring, and the consideration of conditional Category A classification for high-volume spine surgeons where comparable exposures are verified by local clinical practice.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148377808","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A dosemeter for the public based on NaCl pellets for use in radiological or nuclear emergencies.","authors":"Maria Karampiperi, Joel Beazley, Jonathan Eakins, Christopher L Rääf, Christian Bernhardsson","doi":"10.1088/1361-6498/ae8552","DOIUrl":"10.1088/1361-6498/ae8552","url":null,"abstract":"<p><p>Sodium chloride (NaCl) has been proposed as a retrospective and prospective dosemeter for optically stimulated luminescence (OSL) dosimetry. The potential for NaCl pellets for individualised<i>in situ</i>dose assessment during a radiological or nuclear emergency was enhanced by their suitability with a portable OSL reader. The current paper studies the possibility of developing a public dosimetric badge, based on NaCl pellets and commonly available low-cost materials. Copper, aluminium and polylactic acid were tested for reducing the overresponse to low x-ray energies, and the results indicated that copper is the best candidate-material for filtering purposes. Furthermore, the ratio between filtered and unfiltered samples may potentially be used to determine the mean energy of the exposure field in some circumstances. In addition, the NaCl pellets exhibit constant response for air kerma rates between 0.006 and 1.9 Gy min^-1. The fading of the pellets does not present any energy dependence. Air kerma reconstruction with three stimulation modes was investigated, and the reconstructed air kerma deviated from the nominal value between 0.8 and 7.9%, which were within measurement uncertainties. The discrepancy between Monte Carlo simulations of the exposed pellets and the experimental data is possibly due to the intrinsic luminescent efficiency of the salt, which in the current study is assumed constant for the entire energy regime. Alanine, exposed together with the NaCl pellets, was studied for the intercomparison and air kerma rate experiments, and showed accurate air kerma reconstruction, with deviation from the actual doses within ∼1<i>σ</i>, and no significant variation with the air kerma rate. Analysis of the alanine dose estimations investigated the conventional peak-to-peak method alongside a fitting method, which did not lead to any improvements in measurement accuracy.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148377822","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Dose simulation for the MATROSHKA-R experiment onboard the international space station using a high-fidelity model of the Zvezda module.","authors":"Desong Zhang, Jiangyan Shen, Kun Zhu, Qing Li, Hua Li, Liye Liu, Congchong Yan","doi":"10.1088/1361-6498/ae850d","DOIUrl":"10.1088/1361-6498/ae850d","url":null,"abstract":"<p><p>The MATROSHKA-R experiment conducted onboard the International Space Station provided invaluable data on depth-dose distributions for critical human organs exposed to the low Earth orbit (LEO) radiation environment. In this study, a high-fidelity computational model of a tissue-equivalent spherical phantom and a refined geometric representation of the Zvezda module were developed using the Geant4 Monte Carlo toolkit. In contrast to previous studies that relied on simplified cylindrical crew module models, our approach successfully and simultaneously reproduced the measured dose distributions in both the surface pocket detectors and the internal container detectors of the phantom. By correlating phantom depths with anatomical organ positions, organ-specific absorbed doses and dose equivalents were estimated. Simulations revealed that galactic cosmic rays contribute over 60% of the total dose equivalent across all organs, with contribution increasing with depth and reaching up to 81% at specific internal positions. The simulated organ dose equivalents showed close agreement with empirical data, validating the spherical phantom's utility for organ-level radiation studies. This work provides a more realistic computational basis for interpreting MATROSHKA-R measurements, and establishes a validated framework for future organ-level dosimetry studies in low-Earth orbit.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148370542","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Radium in marine sediments and offshore NORM/TENORM: a framework for environmental radiological protection, monitoring and risk assessment.","authors":"Rafael L Rodrigues, Rogério A Filgueiras, Ademir X da Silva","doi":"10.1088/1361-6498/ae8553","DOIUrl":"https://doi.org/10.1088/1361-6498/ae8553","url":null,"abstract":"<p><p>Radium isotopes are central to marine radioecology and environmental radiological protection because they connect natural decay series, sediment-water exchange, offshore oil and gas naturally occurring radioactive material (NORM), technologically enhanced NORM and exposure of humans and non-human biota. Marine sediments are often described as radionuclide repositories, yet for radium they may function as reactive interfaces where activity is generated, adsorbed, coprecipitated, remobilised, buried, resuspended or incorporated into low-solubility sulfate phases such as radiobarite. This review develops a framework-guided synthesis of²²⁶Ra and²²⁸Ra in marine sediments, produced water, NORM scale, oily sludge, sediment-water exchange, analytical methods and radiological risk assessment. The proposed framework organises the evidence into five domains: source terms, host phases, mobility processes, analytical observability and exposure relevance. Recent studies show that produced-water radium can precipitate as micron-sized radiobarite or radiostrontiobarite particles, radium-bearing barite scales may preserve strong mineralogical control over solubility and release and ecological dose assessment depends on exposure geometry, partitioning assumptions, mineral incorporation, progeny ingrowth, sediment mixing depth and organism occupancy. Bulk activity concentration alone is therefore insufficient for interpreting radiological significance. Future monitoring should integrate²²⁶Ra and²²⁸Ra activity, isotope ratios, porewater measurements, Ba-Sr-Ca-SO₄chemistry, mineralogical characterisation, phase-specific activity, leaching tests, site-specific<i>K_d</i>values and tiered dose modelling. By reframing marine sediments as active radium reaction zones, this review provides a practical basis for improved monitoring, offshore NORM management and environmental radiation protection.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":"46 3","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148430921","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Radiation protection knowledge among healthcare professionals and students - what (if anything) are studies telling us?","authors":"Richard W Harbron","doi":"10.1088/1361-6498/ae8271","DOIUrl":"10.1088/1361-6498/ae8271","url":null,"abstract":"","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148334148","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Dose evaluation of medical staff during proximal femur fracture surgery using fluoroscopy.","authors":"Luiz Matheus de Souza Aguiar Leite, Lilian Torres Rezende Ribeiro, Arícia Ravane Pereira da Cruz, Vinícius Saito Monteiro de Barros, Felipe Alves Monte, Thiago Henrique Silveira de Andrade, Júlio César Xavier Filho, Gabriela Rosa Meira, Viviane Khoury Asfora","doi":"10.1088/1361-6498/ae7f2a","DOIUrl":"10.1088/1361-6498/ae7f2a","url":null,"abstract":"<p><p>The use of fluoroscopy in orthopedic interventional procedures has become increasingly common. Although it offers significant clinical advantages by reducing procedural invasiveness, it also exposes both patients and medical staff to ionizing radiation. This study reports occupational dose measurements for surgeons during 40 proximal femur fracture procedures conducted at a reference hospital in Recife, Brazil. The estimated annual effective doses for the leading and auxiliary surgeons were approximately 1.3-1.5 mSv, corresponding to about 7.5% of the annual dose limit (<i>n</i>= 325 procedures yr^-1). The estimated annual eye lens exposures for both surgeons ranged from 4.7-5.8 mSv yr^-1, approaching 30% the current eye lens dose limit. For these procedures, the glabella (forehead) position was identified as the most appropriate location for the eye lens dosimeter. A correlation between<i>H</i>_p(10) values measured externally on the thyroid shield and<i>H</i>_p(3) doses at the glabella suggests that eye lens dose measurements can serve as a preliminary indicator-within ±15%-for determining the need for dedicated eye lens monitoring when annual lens doses may exceed 15 mSv. Dose measurements to the hands varied according to the procedure type and the equipment used. The highest values were observed during complex surgeries, such as complex subtrochanteric fractures with multiple fragments. The frequency of outliers in the hand dose data, observed in approximately 15% of the procedures, is associated with cases in which at least one of the surgeon's hands was exposed to the primary beam. For the leading surgeon, the doses from outliers to the left hand accounted for 58% of the total dose to that hand, whereas for the auxiliary surgeon, 16% of procedures classified as high outliers contributed 75% of the total dose. These findings emphasise the importance of keeping hands outside the primary beam, as even brief direct exposures can significantly increase occupational hand doses.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148279534","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Assessment of the extremity exposure during preparation and administration of¹⁷⁷Lu - results of a multi-center study.","authors":"Robert Kollaard, Łukasz Albiniak, Nicolas Cherbuin, Jérémie Dabin, Hanan Datz, Mahila Ferrari, Mikko Hakulinen, Sigalit Haruz-Waschitz, Tereza Kráčmerová, Ann McCann, Roel Wierts, Alessandra Zorz, Else Aalbersberg","doi":"10.1088/1361-6498/ae826f","DOIUrl":"10.1088/1361-6498/ae826f","url":null,"abstract":"<p><p>Despite the increased use of¹⁷⁷Lu in nuclear medicine (NM) over the last 10 years, the knowledge of the actual exposure of the extremities due to manipulation of this pharmaceutical is limited. The purpose of this study is to assess the extremity dose during the preparation and administration of¹⁷⁷Lu-labelled radiopharmaceuticals in a wide range of NM practices. Workers in 10 NM centres throughout Europe wore a ring dosimeter on the base of the index finger of the non-dominant hand during preparation and/or administration of¹⁷⁷Lu-labelled radiopharmaceuticals. Information on manipulated activity, tasks performed and protection measures was collected to allow sub-analyses. The median ring dose per monitoring interval was 0.16 mSv, with a maximum of 2.27 mSv in one month. The median normalised dose amounted 3.5<i>µ</i>Sv GBq^-1(range 0.5-525). The highest monthly doses were found for workers involved in preparation of the pharmaceutical. The workers performing manual administrations (6.5<i>µ</i>Sv GBq^-1) showed higher normalised ring doses than those using the gravity method (3.5<i>µ</i>Sv GBq^-1) or a syringe pump (1.0<i>µ</i>Sv GBq^-1). Explanations for the wide range of normalised ring doses may be found in the different techniques applied in this study and the differences in minimum reportable doses of the dosimeters. When the data is extrapolated using a fingertip to ring dose ratio of 5, an annual fingertip dose of 1-136 mSv is found, with a median fingertip dose of 10 mSv per year. Extremity exposure during¹⁷⁷Lu handling remained well below dose limits. The highest normalised doses occurred during preparation and manual administration. Overall, this investigation shows doses remain low when appropriate radiation protection measures (e.g. shielding and minimising time at short distance) are being applied.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.7,"publicationDate":"2026-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148334061","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}