Base de dados : MEDLINE
Pesquisa : N06.850.460.100.110 [Categoria DeCS]
Referências encontradas : 2065 [refinar]
Mostrando: 1 .. 10   no formato [Detalhado]

página 1 de 207 ir para página                         

  1 / 2065 MEDLINE  
              next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:29334619
[Au] Autor:Zhang X; Efthimiou G; Wang Y; Huang M
[Ad] Endereço:Institute of Public Safety Research, Department of Engineering Physics, Tsinghua University, Beijing 100084, PR China; Institute for Nuclear and Energy Technologies, Karlsruhe Institute of Technology, Karlsruhe, D-76021, Germany. Electronic address: zhangxiaole10@outlook.com.
[Ti] Título:Comparisons between a new point kernel-based scheme and the infinite plane source assumption method for radiation calculation of deposited airborne radionuclides from nuclear power plants.
[So] Source:J Environ Radioact;184-185:32-45, 2018 Apr.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:Radiation from the deposited radionuclides is indispensable information for environmental impact assessment of nuclear power plants and emergency management during nuclear accidents. Ground shine estimation is related to multiple physical processes, including atmospheric dispersion, deposition, soil and air radiation shielding. It still remains unclear that whether the normally adopted "infinite plane" source assumption for the ground shine calculation is accurate enough, especially for the area with highly heterogeneous deposition distribution near the release point. In this study, a new ground shine calculation scheme, which accounts for both the spatial deposition distribution and the properties of air and soil layers, is developed based on point kernel method. Two sets of "detector-centered" grids are proposed and optimized for both the deposition and radiation calculations to better simulate the results measured by the detectors, which will be beneficial for the applications such as source term estimation. The evaluation against the available data of Monte Carlo methods in the literature indicates that the errors of the new scheme are within 5% for the key radionuclides in nuclear accidents. The comparisons between the new scheme and "infinite plane" assumption indicate that the assumption is tenable (relative errors within 20%) for the area located 1 km away from the release source. Within 1 km range, the assumption mainly causes errors for wet deposition and the errors are independent of rain intensities. The results suggest that the new scheme should be adopted if the detectors are within 1 km from the source under the stable atmosphere (classes E and F), or the detectors are within 500 m under slightly unstable (class C) or neutral (class D) atmosphere. Otherwise, the infinite plane assumption is reasonable since the relative errors induced by this assumption are within 20%. The results here are only based on theoretical investigations. They should be further thoroughly evaluated with real measurements in the future.
[Mh] Termos MeSH primário: Poluentes Radioativos do Ar/análise
Contaminação Radioativa do Ar/estatística & dados numéricos
Centrais Nucleares
Monitoramento de Radiação/métodos
[Mh] Termos MeSH secundário: Atmosfera
Modelos Teóricos
Método de Monte Carlo
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Air Pollutants, Radioactive)
[Em] Mês de entrada:1802
[Cu] Atualização por classe:180220
[Lr] Data última revisão:
180220
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:180116
[St] Status:MEDLINE


  2 / 2065 MEDLINE  
              first record previous record next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:29306093
[Au] Autor:Tsapalov A; Kovler K
[Ad] Endereço:Scientific & Technical Centre "AMPLITUDA", Gen. Alekseeva 15, Zelenograd, Moscow, Russia.
[Ti] Título:Indoor radon regulation using tabulated values of temporal radon variation.
[So] Source:J Environ Radioact;183:59-72, 2018 Mar.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:Mass measurements of indoor radon concentrations have been conducted for about 30 years. In most of the countries, a national reference/action/limit level is adopted, limiting the annual average indoor radon (AAIR) concentration. However, until now, there is no single and generally accepted international protocol for determining the AAIR with a known confidence interval, based on measurements of different durations. Obviously, as the duration of measurements increases, the uncertainty of the AAIR estimation decreases. The lack of the information about the confidence interval of the determined AAIR level does not allow correct comparison with the radon reference level. This greatly complicates development of an effective indoor radon measurement protocol and strategy. The paper proposes a general principle of indoor radon regulation, based on the simple criteria widely used in metrology, and introduces a new parameter - coefficient of temporal radon variation K (t) that depends on the measurement duration and determines the uncertainty of the AAIR. An algorithm for determining K (t) based on the results of annual continuous radon monitoring in experimental rooms is proposed. Included are indoor radon activity concentrations and equilibrium equivalent concentration (EEC) of radon progeny. The monitoring was conducted in 10 selected experimental rooms located in 7 buildings, mainly in the Moscow region (Russia), from 2006 to 2013. The experimental and tabulated values of K (t) and also the values of the coefficient of temporal EEC variation depending on the mode and duration of the measurements were obtained. The recommendations to improve the efficiency and reliability of indoor radon regulation are given. The importance of taking into account the geological factors is discussed. The representativity of the results of the study is estimated and the approach for their verification is proposed.
[Mh] Termos MeSH primário: Poluentes Radioativos do Ar/análise
Poluição do Ar em Ambientes Fechados/prevenção & controle
Contaminação Radioativa do Ar/prevenção & controle
Monitoramento de Radiação/métodos
Radônio/análise
[Mh] Termos MeSH secundário: Poluição do Ar em Ambientes Fechados/análise
Poluição do Ar em Ambientes Fechados/estatística & dados numéricos
Contaminação Radioativa do Ar/análise
Contaminação Radioativa do Ar/estatística & dados numéricos
Produtos de Decaimento de Radônio
Reprodutibilidade dos Testes
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Air Pollutants, Radioactive); 0 (Radon Daughters); Q74S4N8N1G (Radon)
[Em] Mês de entrada:1801
[Cu] Atualização por classe:180130
[Lr] Data última revisão:
180130
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:180107
[St] Status:MEDLINE


  3 / 2065 MEDLINE  
              first record previous record next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:29278800
[Au] Autor:Leung WH; Ma WM; Chan PKY
[Ad] Endereço:Hong Kong Observatory, Hong Kong, China. Electronic address: whleung@hko.gov.hk.
[Ti] Título:Nuclear accident consequence assessment in Hong Kong using JRODOS.
[So] Source:J Environ Radioact;183:27-36, 2018 Mar.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:The JRODOS (Java-based Real-time Online DecisiOn Support) is a decision support system for off-site emergency management for releases of radioactive material into the environment. This paper documents the application of JRODOS by the Hong Kong Observatory in accident consequence assessment and emergency preparedness studies. For operational considerations, the most computational efficient dispersion model in JRODOS, ATSTEP, is adopted. Verification studies for JRODOS's ATSTEP model have been conducted. Comparison with tracer experiment results showed that under neutral atmospheric conditions and distances up to 50 km, the JRODOS simulation outputs were in general of the same order of magnitude with the tracer data. To further evaluate the capability of JRODOS in short-range simulation, a case study on the Fukushima nuclear power plant accident was also carried out. JRODOS was able to produce realistic simulation results which were comparable to the actual airborne monitoring data of the Cs-137 ground deposition from the Fukushima accident. Furthermore, the results of a comprehensive study to assess the potential consequences of accidents at a nearby nuclear power station are presented. Simulation using the French S3 source term for the Guangdong Nuclear Power Station at Daya Bay showed that the projected effective doses within Hong Kong remain far below the IAEA generic criteria of projected dose for urgent protective actions in sheltering/evacuation, while the projected equivalent dose in thyroid may meet the IAEA generic criteria for use of thyroid blocking agent at some areas in the northeastern part of Hong Kong, at distances of up to about 40 km from Daya Bay depending on the prevailing weather conditions in different seasons.
[Mh] Termos MeSH primário: Poluentes Radioativos do Ar/análise
Defesa Civil/métodos
Liberação Nociva de Radioativos
[Mh] Termos MeSH secundário: Contaminação Radioativa do Ar/estatística & dados numéricos
Radioisótopos de Césio/análise
Hong Kong
Dose de Radiação
Monitoramento de Radiação/métodos
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Air Pollutants, Radioactive); 0 (Cesium Radioisotopes)
[Em] Mês de entrada:1801
[Cu] Atualização por classe:180130
[Lr] Data última revisão:
180130
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:171227
[St] Status:MEDLINE


  4 / 2065 MEDLINE  
              first record previous record next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:29179047
[Au] Autor:Leelossy Á; Lagzi I; Kovács A; Mészáros R
[Ad] Endereço:Department of Meteorology, Eötvös Loránd University, P.O. Box 32, H-1518, Budapest, Hungary. Electronic address: leeladam@caesar.elte.hu.
[Ti] Título:A review of numerical models to predict the atmospheric dispersion of radionuclides.
[So] Source:J Environ Radioact;182:20-33, 2018 Feb.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:The field of atmospheric dispersion modeling has evolved together with nuclear risk assessment and emergency response systems. Atmospheric concentration and deposition of radionuclides originating from an unintended release provide the basis of dose estimations and countermeasure strategies. To predict the atmospheric dispersion and deposition of radionuclides several numerical models are available coupled with numerical weather prediction (NWP) systems. This work provides a review of the main concepts and different approaches of atmospheric dispersion modeling. Key processes of the atmospheric transport of radionuclides are emission, advection, turbulent diffusion, dry and wet deposition, radioactive decay and other physical and chemical transformations. A wide range of modeling software are available to simulate these processes with different physical assumptions, numerical approaches and implementation. The most appropriate modeling tool for a specific purpose can be selected based on the spatial scale, the complexity of meteorology, land surface and physical and chemical transformations, also considering the available data and computational resource. For most regulatory and operational applications, offline coupled NWP-dispersion systems are used, either with a local scale Gaussian, or a regional to global scale Eulerian or Lagrangian approach. The dispersion model results show large sensitivity on the accuracy of the coupled NWP model, especially through the description of planetary boundary layer turbulence, deep convection and wet deposition. Improvement of dispersion predictions can be achieved by online coupling of mesoscale meteorology and atmospheric transport models. The 2011 Fukushima event was the first large-scale nuclear accident where real-time prognostic dispersion modeling provided decision support. Dozens of dispersion models with different approaches were used for prognostic and retrospective simulations of the Fukushima release. An unknown release rate proved to be the largest factor of uncertainty, underlining the importance of inverse modeling and data assimilation in future developments.
[Mh] Termos MeSH primário: Contaminação Radioativa do Ar/estatística & dados numéricos
Modelos Teóricos
Monitoramento de Radiação/métodos
[Mh] Termos MeSH secundário: Atmosfera/química
Radioisótopos de Césio/análise
Estudos Retrospectivos
[Pt] Tipo de publicação:JOURNAL ARTICLE; REVIEW
[Nm] Nome de substância:
0 (Cesium Radioisotopes)
[Em] Mês de entrada:1712
[Cu] Atualização por classe:171228
[Lr] Data última revisão:
171228
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:171128
[St] Status:MEDLINE


  5 / 2065 MEDLINE  
              first record previous record next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:29175007
[Au] Autor:Dempsey S; Lyons S; Nolan A
[Ad] Endereço:The Economic and Social Research Institute, Sir John Rogerson's Quay, Dublin 2, Ireland.
[Ti] Título:High Radon Areas and lung cancer prevalence: Evidence from Ireland.
[So] Source:J Environ Radioact;182:12-19, 2018 Feb.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:This paper examined the relationship between radon risk and lung cancer prevalence using a novel dataset combining spatially-coded survey data with a radon risk map. A logit model was employed to test for significant associations between a high risk of indoor radon and lung cancer prevalence using data on 5590 people aged 50+ from The Irish Longitudinal Study on Ageing (TILDA) and radon risk data from Ireland's Environmental Protection Agency (EPA). The use of data at the individual level allowed a wide range of potentially confounding factors (such as smoking) to be included. Results indicate that those who lived in an area in which 10%-20% of households were above the national reference level (200 Bq/m ) were 2.9-3.1 times more likely to report a lung cancer diagnosis relative to those who lived in areas in which less than 1% of households were above the national reference level.
[Mh] Termos MeSH primário: Poluição do Ar em Ambientes Fechados/análise
Contaminação Radioativa do Ar/estatística & dados numéricos
Exposição Ambiental/estatística & dados numéricos
Neoplasias Pulmonares/epidemiologia
Radônio/análise
[Mh] Termos MeSH secundário: Poluição do Ar em Ambientes Fechados/estatística & dados numéricos
Habitação/estatística & dados numéricos
Seres Humanos
Irlanda/epidemiologia
Masculino
Prevalência
Monitoramento de Radiação
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
Q74S4N8N1G (Radon)
[Em] Mês de entrada:1712
[Cu] Atualização por classe:171228
[Lr] Data última revisão:
171228
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:171128
[St] Status:MEDLINE


  6 / 2065 MEDLINE  
              first record previous record next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:29175006
[Au] Autor:Viner BJ; Jannik T; Hepworth A; Adetona O; Naeher L; Eddy T; Doman E; Blake J
[Ad] Endereço:Savannah River National Laboratory, USA. Electronic address: brian.viner@srnl.doe.gov.
[Ti] Título:Predicted cumulative dose to firefighters and the offsite public from natural and anthropogenic radionuclides in smoke from wildland fires at the Savannah River Site, South Carolina USA.
[So] Source:J Environ Radioact;182:1-11, 2018 Feb.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:The contaminated ground surface at Savannah River Site (SRS) is a result of the decades of work that has been performed maintaining the country's nuclear stockpile and performing research and development on nuclear materials. The volatilization of radionuclides during wildfire results in airborne particles that are dispersed within the smoke plume and may result in doses to downwind firefighters and the public. To better understand the risk that these smoke plumes present, we have characterized four regions at SRS in terms of their fuel characteristics and radiological contamination on the ground. Combined with general meteorological conditions describing typical and extreme burn conditions, we have simulated potential fires in these regions and predicted the potential radiological dose that could be received by firefighting personnel and the public surrounding the SRS. In all cases, the predicted cumulative dose was a small percent of the US Department of Energy regulatory limit (0.25 mSv). These predictions were conservative and assumed that firefighters would be exposed for the duration of their shift and the public would be exposed for the entire day over the duration of the burn. Realistically, firefighters routinely rotate off the firefront during their shift and the public would likely remain indoors much of the day. However, we show that even under worst-case conditions the regulatory limits are not exceeded. We can infer that the risks associated with wildfires would not be expected to cause cumulative doses above the level of concern to either responding personnel or the offsite public.
[Mh] Termos MeSH primário: Poluentes Ocupacionais do Ar/análise
Poluentes Radioativos do Ar/análise
Contaminação Radioativa do Ar/estatística & dados numéricos
Exposição Ocupacional/estatística & dados numéricos
Incêndios Florestais/estatística & dados numéricos
[Mh] Termos MeSH secundário: Bombeiros
Radioisótopos
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Air Pollutants, Occupational); 0 (Air Pollutants, Radioactive); 0 (Radioisotopes)
[Em] Mês de entrada:1712
[Cu] Atualização por classe:171228
[Lr] Data última revisão:
171228
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:171128
[St] Status:MEDLINE


  7 / 2065 MEDLINE  
              first record previous record next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:28542014
[Au] Autor:Scofield PA; Smith LL; Johnson DN
[Ad] Endereço:*Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN, 37831.
[Ti] Título:Oak Ridge Reservation Environmental Protection Rad Neshaps Radionuclide Inventory Web Database and Rad Neshaps Source and Dose Database.
[So] Source:Health Phys;113(1):78-88, 2017 Jul.
[Is] ISSN:1538-5159
[Cp] País de publicação:United States
[La] Idioma:eng
[Ab] Resumo:The U.S. Environmental Protection Agency promulgated national emission standards for emissions of radionuclides other than radon from US Department of Energy facilities in Chapter 40 of the Code of Federal Regulations (CFR) 61, Subpart H. This regulatory standard limits the annual effective dose that any member of the public can receive from Department of Energy facilities to 0.1 mSv. As defined in the preamble of the final rule, all of the facilities on the Oak Ridge Reservation, i.e., the Y-12 National Security Complex, Oak Ridge National Laboratory, East Tennessee Technology Park, and any other U.S. Department of Energy operations on Oak Ridge Reservation, combined, must meet the annual dose limit of 0.1 mSv. At Oak Ridge National Laboratory, there are monitored sources and numerous unmonitored sources. To maintain radiological source and inventory information for these unmonitored sources, e.g., laboratory hoods, equipment exhausts, and room exhausts not currently venting to monitored stacks on the Oak Ridge National Laboratory campus, the Environmental Protection Rad NESHAPs Inventory Web Database was developed. This database is updated annually and is used to compile emissions data for the annual Radionuclide National Emission Standards for Hazardous Air Pollutants (Rad NESHAPs) report required by 40 CFR 61.94. It also provides supporting documentation for facility compliance audits. In addition, a Rad NESHAPs source and dose database was developed to import the source and dose summary data from Clean Air Act Assessment Package-1988 computer model files. This database provides Oak Ridge Reservation and facility-specific source inventory; doses associated with each source and facility; and total doses for the Oak Ridge Reservation dose.
[Mh] Termos MeSH primário: Contaminação Radioativa do Ar/estatística & dados numéricos
Sistemas de Gerenciamento de Base de Dados/organização & administração
Bases de Dados Factuais
Internet/organização & administração
Monitoramento de Radiação/estatística & dados numéricos
Proteção Radiológica/estatística & dados numéricos
[Mh] Termos MeSH secundário: Programas Governamentais
Armazenamento e Recuperação da Informação/métodos
Tennessee
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Em] Mês de entrada:1708
[Cu] Atualização por classe:170818
[Lr] Data última revisão:
170818
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170526
[St] Status:MEDLINE
[do] DOI:10.1097/HP.0000000000000682


  8 / 2065 MEDLINE  
              first record previous record next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:28350698
[Au] Autor:McNaughton MW; Gillis JM; Ruedig E; Whicker JJ; Fuehne DP
[Ad] Endereço:*MS J978, Los Alamos National Laboratory, MS J978, Los Alamos, NM 87544.
[Ti] Título:Gamma-Ray Dose From an Overhead Plume.
[So] Source:Health Phys;112(5):445-450, 2017 May.
[Is] ISSN:1538-5159
[Cp] País de publicação:United States
[La] Idioma:eng
[Ab] Resumo:Standard plume models can underestimate the gamma-ray dose when most of the radioactive material is above the heads of the receptors. Typically, a model is used to calculate the air concentration at the height of the receptor, and the dose is calculated by multiplying the air concentration by a concentration-to-dose conversion factor. Models indicate that if the plume is emitted from a stack during stable atmospheric conditions, the lower edges of the plume may not reach the ground, in which case both the ground-level concentration and the dose are usually reported as zero. However, in such cases, the dose from overhead gamma-emitting radionuclides may be substantial. Such underestimates could impact decision making in emergency situations. The Monte Carlo N-Particle code, MCNP, was used to calculate the overhead shine dose and to compare with standard plume models. At long distances and during unstable atmospheric conditions, the MCNP results agree with the standard models. At short distances, where many models calculate zero, the true dose (as modeled by MCNP) can be estimated with simple equations.
[Mh] Termos MeSH primário: Contaminação Radioativa do Ar/estatística & dados numéricos
Raios gama
Modelos Estatísticos
Exposição à Radiação/estatística & dados numéricos
Liberação Nociva de Radioativos/estatística & dados numéricos
Radioisótopos/análise
[Mh] Termos MeSH secundário: Ar/análise
Simulação por Computador
Seres Humanos
Dose de Radiação
Vento
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Radioisotopes)
[Em] Mês de entrada:1707
[Cu] Atualização por classe:170703
[Lr] Data última revisão:
170703
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170329
[St] Status:MEDLINE
[do] DOI:10.1097/HP.0000000000000643


  9 / 2065 MEDLINE  
              first record previous record next record last record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:28234692
[Au] Autor:Stagich BH; Moore KR; Newton JR; Dixon KL; Jannik GT
[Ad] Endereço:*Augusta University, Department of Chemistry and Physics, 1120 15th Street, Augusta, GA; †Savannah River National Laboratory, Savannah River Nuclear Solutions, Savannah River Site, Aiken, SC.
[Ti] Título:Dose Comparisons for a Site-specific Representative Person Using the Age-dependent Dose Coefficients in CAP88-PC Version 4.
[So] Source:Health Phys;112(4):338-342, 2017 Apr.
[Is] ISSN:1538-5159
[Cp] País de publicação:United States
[La] Idioma:eng
[Ab] Resumo:Most U.S. Department of Energy (DOE) facilities with radiological airborne releases use the U.S. Environmental Protection Agency's (EPA) environmental dosimetry code CAP88-PC to demonstrate compliance with regulations in 40CFR61, subpart H [National Emission Standards for Hazardous Air Pollutants: Radiological (NESHAP)]. In 2015, EPA released Version 4 of CAP88-PC, which included significant modifications that improved usability and age-dependent dose coefficients and usage factors for six age groups (infant, 1 y, 5 y, 10 y, 15 y, and adult). However, EPA has not yet provided specific guidance on how to use these age-dependent factors. For demonstrating compliance with DOE public dose regulations, the Savannah River Site (SRS) recently changed from using the maximally exposed individual (MEI) concept (adult male) to the representative person concept (age- and gender-averaged reference person). In this study, dose comparisons are provided between the MEI and a SRS-specific representative person using the age-specific dose coefficients and usage factors in CAP88-PC V.4. Dose comparisons also are provided for each of the six age groups using five radionuclides of interest at SRS (tritium oxide, Cs, Sr, Pu, and I). In general, the total effective dose increases about 11% for the representative person as compared to the current NESHAP MEI because of the inclusion of the more radiosensitive age groups.
[Mh] Termos MeSH primário: Envelhecimento/fisiologia
Contaminação Radioativa do Ar/estatística & dados numéricos
Modelos Estatísticos
Exposição à Radiação/análise
Liberação Nociva de Radioativos/estatística & dados numéricos
Radioisótopos/análise
[Mh] Termos MeSH secundário: Adolescente
Adulto
Contaminação Radioativa do Ar/análise
Criança
Pré-Escolar
Simulação por Computador
Feminino
Seres Humanos
Lactente
Recém-Nascido
Masculino
Meia-Idade
Dose de Radiação
Proteção Radiológica/métodos
Reprodutibilidade dos Testes
Sensibilidade e Especificidade
Software
Validação de Programas de Computador
Adulto Jovem
[Pt] Tipo de publicação:COMPARATIVE STUDY; EVALUATION STUDIES; JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Radioisotopes)
[Em] Mês de entrada:1706
[Cu] Atualização por classe:170630
[Lr] Data última revisão:
170630
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170225
[St] Status:MEDLINE
[do] DOI:10.1097/HP.0000000000000633


  10 / 2065 MEDLINE  
              first record previous record
seleciona
para imprimir
Fotocópia
Texto completo
[PMID]:28187334
[Au] Autor:Hasegawa H; Kakiuchi H; Akata N; Ohtsuka Y; Hisamatsu S
[Ad] Endereço:Department of Radioecology, Institute for Environmental Sciences, 1-7 Ienomae, Obuchi, Rokkasho, Kamikita, Aomori 039-3212, Japan. Electronic address: hhidenao@ies.or.jp.
[Ti] Título:Regional and global contributions of anthropogenic iodine-129 in monthly deposition samples collected in North East Japan between 2006 and 2015.
[So] Source:J Environ Radioact;171:65-73, 2017 May.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:We measured the monthly atmospheric deposition flux of I at Rokkasho, Aomori, Japan-the location of a commercial spent nuclear fuel reprocessing plant-from 2006 to 2015 to assess the impact of the plant on environmental I levels. The plant is now under final safety assessment by a national authority after test operation using actual spent nuclear fuel. During cutting and chemical processing in test operations from April 2006 to October 2008, I was discharged to the atmosphere and detected in our deposition samples. I deposition fluxes largely followed the discharge pattern of I from the plant to the atmosphere, and most of the deposited I originated from the plant. In and after 2009, I deposition fluxes decreased dramatically to reach the background level; the I deposition fluxes at Rokkasho were almost the same as those at Hirosaki, where an additional sampling point was set up as a background site 85 km from the plant in 2011. The background I deposition fluxes showed seasonal variation-high in winter and low in the other seasons-at both Rokkasho and Hirosaki. The results of a backward trajectory analysis of the air mass at Rokkasho suggested that reprocessing plants in Europe were the origins of the high I flux in winter. The contribution of I released from the Fukushima Dai-ichi Nuclear Power Plant accident to the I deposition flux at Rokkasho in 2011 was small on the basis of the I/ I activity ratio.
[Mh] Termos MeSH primário: Poluentes Radioativos do Ar/análise
Contaminação Radioativa do Ar/estatística & dados numéricos
Acidente Nuclear de Fukushima
Radioisótopos do Iodo/análise
Monitoramento de Radiação
[Mh] Termos MeSH secundário: Atmosfera/química
Japão
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Air Pollutants, Radioactive); 0 (Iodine Radioisotopes)
[Em] Mês de entrada:1704
[Cu] Atualização por classe:170428
[Lr] Data última revisão:
170428
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170211
[St] Status:MEDLINE



página 1 de 207 ir para página                         
   


Refinar a pesquisa
  Base de dados : MEDLINE Formulário avançado   

    Pesquisar no campo  
1  
2
3
 
           



Search engine: iAH v2.6 powered by WWWISIS

BIREME/OPAS/OMS - Centro Latino-Americano e do Caribe de Informação em Ciências da Saúde