Base de dados : MEDLINE
Pesquisa : G01.828 [Categoria DeCS]
Referências encontradas : 1244 [refinar]
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[PMID]:29407639
[Au] Autor:Thanh TT; Vuong LQ; Ho PL; Chuong HD; Nguyen VH; Tao CV
[Ad] Endereço:Department of Nuclear Physics, Faculty of Physics and Engineering Physics, VNUHCM-University of Science, 227, Nguyen Van Cu Street, District 5, Ho Chi Minh City, Viet Nam; Nuclear Technique Laboratory, VNUHCM-University of Science, 227, Nguyen Van Cu Street, District 5, Ho Chi Minh City, Viet Nam. E
[Ti] Título:Validation of an advanced analytical procedure applied to the measurement of environmental radioactivity.
[So] Source:J Environ Radioact;184-185:109-113, 2018 Apr.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:In this work, an advanced analytical procedure was applied to calculate radioactivity in spiked water samples in a close geometry gamma spectroscopy. It included MCNP-CP code in order to calculate the coincidence summing correction factor (CSF). The CSF results were validated by a deterministic method using ETNA code for both p-type HPGe detectors. It showed that a good agreement for both codes. Finally, the validity of the developed procedure was confirmed by a proficiency test to calculate the activities of various radionuclides. The results of the radioactivity measurement with both detectors using the advanced analytical procedure were received the ''Accepted'' statuses following the proficiency test.
[Mh] Termos MeSH primário: Monitoramento de Radiação/métodos
Poluentes Radioativos/análise
Radioatividade
[Mh] Termos MeSH secundário: Meio Ambiente
Raios gama
[Pt] Tipo de publicação:JOURNAL ARTICLE; VALIDATION STUDIES
[Nm] Nome de substância:
0 (Radioactive Pollutants)
[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:180207
[St] Status:MEDLINE


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[PMID]:28749812
[Au] Autor:Iwaoka K; Yajima K; Suzuki T; Yonehara H; Hosoda M; Tokonami S; Kanda R
[Ad] Endereço:*National Institutes for Quantum and Radiological Science and Technology, 4-9-1 Anagawa, Inage, Chiba 263-8555, Japan; †Institute of Radiation Emergency Medicine, Hirosaki University, 66-1 Honcho, Hirosaki, Aomori 036-8564, Japan; ‡National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage, Chiba 263-8555, Japan; §Hirosaki University Graduate School of Health Sciences, 66-1 Honcho, Hirosaki, Aomori 036-8564, Japan.
[Ti] Título:Investigation of Natural Radioactivity in a Monazite Processing Plant in Japan.
[So] Source:Health Phys;113(3):220-224, 2017 09.
[Is] ISSN:1538-5159
[Cp] País de publicação:United States
[La] Idioma:eng
[Ab] Resumo:Monazite is a naturally occurring radioactive material that is processed for use in a variety of domestic applications. At present, there is little information available on potential radiation doses experienced by people working with monazite. The ambient dose rate and activity concentration of natural radionuclides in raw materials, products, and dust in work sites as well as the Rn and Rn concentrations in work sites were measured in a monazite processing plant in Japan. Dose estimations for plant workers were also conducted. The activity concentration of the U series in raw materials and products for the monazite processing plant was found to be higher than the relevant values described in the International Atomic Energy Agency Safety Standards. The ambient dose rates in the raw material yard were higher than those in other work sites. Moreover, the activity concentrations of dust in the milling site were higher than those in other work sites. The Rn concentrations in all work sites were almost the same as those in regular indoor environments in Japan. The Rn concentrations in all work sites were much higher than those in regular indoor environments in Japan. The maximum value of the effective dose for workers was 0.62 mSv y, which is lower than the reference level range (1-20 mSv y) for abnormally high levels of natural background radiation published in the International Commission of Radiological Protection Publication 103.
[Mh] Termos MeSH primário: Metais Terras Raras/química
Monitoramento de Radiação
[Mh] Termos MeSH secundário: Radiação de Fundo
Poeira/análise
Seres Humanos
Japão
Radioatividade
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Dust); 0 (Metals, Rare Earth); 1306-41-8 (monazite)
[Em] Mês de entrada:1708
[Cu] Atualização por classe:180214
[Lr] Data última revisão:
180214
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170728
[St] Status:MEDLINE
[do] DOI:10.1097/HP.0000000000000692


  3 / 1244 MEDLINE  
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[PMID]:29291453
[Au] Autor:Lindborg T; Thorne M; Andersson E; Becker J; Brandefelt J; Cabianca T; Gunia M; Ikonen ATK; Johansson E; Kangasniemi V; Kautsky U; Kirchner G; Klos R; Kowe R; Kontula A; Kupiainen P; Lahdenperä AM; Lord NS; Lunt DJ; Näslund JO; Nordén M; Norris S; Pérez-Sánchez D; Proverbio A; Riekki K; Rübel A; Sweeck L; Walke R; Xu S; Smith G; Pröhl G
[Ad] Endereço:Svensk Kärnbränslehantering AB, Evenemangsgatan 13, 169 79, Solna, Sweden. Electronic address: Tobias.Lindborg@skb.se.
[Ti] Título:Climate change and landscape development in post-closure safety assessment of solid radioactive waste disposal: Results of an initiative of the IAEA.
[So] Source:J Environ Radioact;183:41-53, 2018 Mar.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:The International Atomic Energy Agency has coordinated an international project addressing climate change and landscape development in post-closure safety assessments of solid radioactive waste disposal. The work has been supported by results of parallel on-going research that has been published in a variety of reports and peer reviewed journal articles. The project is due to be described in detail in a forthcoming IAEA report. Noting the multi-disciplinary nature of post-closure safety assessments, here, an overview of the work is given to provide researchers in the broader fields of radioecology and radiological safety assessment with a review of the work that has been undertaken. It is hoped that such dissemination will support and promote integrated understanding and coherent treatment of climate change and landscape development within an overall assessment process. The key activities undertaken in the project were: identification of the key processes that drive environmental change (mainly those associated with climate and climate change), and description of how a relevant future may develop on a global scale; development of a methodology for characterising environmental change that is valid on a global scale, showing how modelled global changes in climate can be downscaled to provide information that may be needed for characterising environmental change in site-specific assessments, and illustrating different aspects of the methodology in a number of case studies that show the evolution of site characteristics and the implications for the dose assessment models. Overall, the study has shown that quantitative climate and landscape modelling has now developed to the stage that it can be used to define an envelope of climate and landscape change scenarios at specific sites and under specific greenhouse-gas emissions assumptions that is suitable for use in quantitative post-closure performance assessments. These scenarios are not predictions of the future, but are projections based on a well-established understanding of the important processes involved and their impacts on different types of landscape. Such projections support the understanding of, and selection of, plausible ranges of scenarios for use in post-closure safety assessments.
[Mh] Termos MeSH primário: Mudança Climática
Resíduos Radioativos/análise
Eliminação de Resíduos/métodos
[Mh] Termos MeSH secundário: Modelos Teóricos
Monitoramento de Radiação
Radioatividade
Medição de Risco
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Radioactive Waste)
[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:180102
[St] Status:MEDLINE


  4 / 1244 MEDLINE  
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[PMID]:29227875
[Au] Autor:Doyi INY; Essumang DK; Agyapong AK; Asumadu-Sarkodie S
[Ad] Endereço:Radioactive Waste Management Centre, Ghana Atomic Energy Commission, P. O. Box LG 80, Legon, Accra, Ghana; Department of Environmental Sciences, Faculty of Science and Engineering, Macquarie University, Sydney, NSW 2109, Australia. Electronic address: i.doyi@gaecgh.org.
[Ti] Título:Soil-to-cassava transfer of naturally occurring radionuclides from communities along Ghana's oil and gas rich Tano Basin.
[So] Source:J Environ Radioact;182:138-141, 2018 Feb.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:Soil-to-plant transfer factor (TF) is widely used to assess the impact of soil radioactivity on agricultural crops. The root crop cassava (Manihot esculenta) provides 30%-50% of the calories consumed in Sub-Saharan Africa and is widely used in South America. γ-ray analysis was used to measure activity concentrations of U, Th, and K in cassava root and soil. The TF values for U, Th, and K were in the range 0.06-0.12, 0.01-0.10 and 0.04-0.28 respectively. The median transfer factors were 0.10 ( U), 0.04 ( Th) and 0.08 ( K). For U and Th, the highest TF values were 0.12 and 0.10 respectively.
[Mh] Termos MeSH primário: Manihot/química
Monitoramento de Radiação
Poluentes Radioativos do Solo/análise
[Mh] Termos MeSH secundário: Radiação de Fundo
Gana
Radioatividade
Solo/química
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Soil); 0 (Soil Pollutants, Radioactive)
[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:171212
[St] Status:MEDLINE


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[PMID]:29182917
[Au] Autor:Ribeiro FCA; Silva JIR; Lima ESA; do Amaral Sobrinho NMB; Perez DV; Lauria DC
[Ad] Endereço:Institute of Radiation Protection and Dosimetry (IRD), Brazilian National Commission on Nuclear Energy (CNEN), Av. Salvador Allende, s/n, Barra da Tijuca, Rio de Janeiro, RJ 22783-127 Brazil. Electronic address: fribeiro@ird.gov.br.
[Ti] Título:Natural radioactivity in soils of the state of Rio de Janeiro (Brazil): Radiological characterization and relationships to geological formation, soil types and soil properties.
[So] Source:J Environ Radioact;182:34-43, 2018 Feb.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:Located in the south-western part of Brazil, the state of Rio de Janeiro is geotectonically contained within a complex structural province that resulted in the amalgamation of the Western Gondwana Paleocontinent. To undertake an extensive radiological characterization of this complex geological province and investigate the influence of bedrock, soil type and soil chemical-physical characteristics on natural radionuclide levels in soils, 259 surface soil samples were collected that encompassed the main soil types and geological formations throughout the state. Gamma spectrometry analysis of the samples resulted in median values of 114 Bq.kg for K, 32 Bq.kg for Ra and 74 Bq.kg for Ra. The median value for Ra was similar to the world median value for soils, the K value was well below the worldwide value, and that for Ra exceeded the world median value. The intense weathering caused by the high rainfall rates and high temperatures may be responsible for the low levels of K in the soils, of which the strongly acidic and clayey soils are markedly K-depleted. A soil from a high-grade metamorphic rock (granulite) presented the lowest Ra (18 Bq.kg ) content, whereas the highest levels for Ra (92 Bq.kg ) and Ra (139 Bq.kg 1) were observed in a young soil enriched in primary minerals (Leptsol). A lowland soil (Gleysol) showed the highest median of K (301 Bq.kg ). Strongly acidic soils tended to present high amounts of Ra, and sandy soils tended to contain low levels of Ra. The external radiation dose indicates that the state has a background radiation level within the natural range.
[Mh] Termos MeSH primário: Monitoramento de Radiação
Poluentes Radioativos do Solo/análise
Solo/química
[Mh] Termos MeSH secundário: Radiação de Fundo
Brasil
Radioisótopos de Potássio/análise
Radioatividade
Rádio (Elemento)/análise
Tório/análise
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Potassium Radioisotopes); 0 (Soil); 0 (Soil Pollutants, Radioactive); 60YU5MIG9W (Thorium); W90AYD6R3Q (Radium)
[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:171129
[St] Status:MEDLINE


  6 / 1244 MEDLINE  
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[PMID]:28796752
[Au] Autor:Ji YY; Kim CJ; Lim KS; Lee W; Chang HS; Chung KH
[Ad] Endereço:*Environmental Radioactivity Assessment Team, Korea Atomic Energy Research Institute, Daejeon 34057, Republic of Korea; † SI Detection Co. Ltd., Daejeon 34051, Republic of Korea.
[Ti] Título:A New Approach for the Determination of Dose Rate and Radioactivity for Detected Gamma Nuclides Using an Environmental Radiation Monitor Based on an NaI(Tl) Detector.
[So] Source:Health Phys;113(4):304-314, 2017 Oct.
[Is] ISSN:1538-5159
[Cp] País de publicação:United States
[La] Idioma:eng
[Ab] Resumo:To expand the application of dose rate spectroscopy to the environment, the method using an environmental radiation monitor (ERM) based on a 3' × 3' NaI(Tl) detector was used to perform real-time monitoring of the dose rate and radioactivity for detected gamma nuclides in the ground around an ERM. Full-energy absorption peaks in the energy spectrum for dose rate were first identified to calculate the individual dose rates of Bi, Ac, Tl, and K distributed in the ground through interference correction because of the finite energy resolution of the NaI(Tl) detector used in an ERM. The radioactivity of the four natural radionuclides was then calculated from the in situ calibration factor-that is, the dose rate per unit curie-of the used ERM for the geometry of the ground in infinite half-space, which was theoretically estimated by Monte Carlo simulation. By an intercomparison using a portable HPGe and samples taken from the ground around an ERM, this method to calculate the dose rate and radioactivity of four nuclides using an ERM was experimentally verified and finally applied to remotely monitor them in real-time in the area in which the ERM had been installed.
[Mh] Termos MeSH primário: Monitoramento Ambiental/métodos
Raios gama
Monitoramento de Radiação/métodos
[Mh] Termos MeSH secundário: Monitoramento Ambiental/instrumentação
Método de Monte Carlo
Dose de Radiação
Monitoramento de Radiação/instrumentação
Radioatividade
Radioisótopos/análise
Espectrometria gama/métodos
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Radioisotopes)
[Em] Mês de entrada:1709
[Cu] Atualização por classe:170915
[Lr] Data última revisão:
170915
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170811
[St] Status:MEDLINE
[do] DOI:10.1097/HP.0000000000000706


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[PMID]:28796751
[Au] Autor:Asano Y
[Ad] Endereço:*Spring-8 Center/RIKEN, 1-1 Koto, Sayo, Hyogo 679-5148, Japan.
[Ti] Título:Estimation of Airborne Radioactivity Induced by 8-GeV-Class Electron LINAC Accelerator.
[So] Source:Health Phys;113(4):237-245, 2017 Oct.
[Is] ISSN:1538-5159
[Cp] País de publicação:United States
[La] Idioma:eng
[Ab] Resumo:Airborne radioactivity induced by high-energy electrons from 6 to 10 GeV is estimated by using analytical methods and the Monte Carlo codes PHITS and FLUKA. Measurements using a gas monitor with a NaI(Tl) scintillator are carried out in air from a dump room at SACLA, an x-ray free-electron laser facility with 7.8-GeV electrons and are compared to the simulations.
[Mh] Termos MeSH primário: Poluentes Radioativos do Ar
Síncrotrons
[Mh] Termos MeSH secundário: Monitoramento Ambiental/métodos
Exposição por Inalação
Método de Monte Carlo
Radioatividade
Contagem de Cintilação/métodos
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Air Pollutants, Radioactive)
[Em] Mês de entrada:1709
[Cu] Atualização por classe:170915
[Lr] Data última revisão:
170915
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170811
[St] Status:MEDLINE
[do] DOI:10.1097/HP.0000000000000700


  8 / 1244 MEDLINE  
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[PMID]:28472753
[Au] Autor:Asic A; Kurtovic-Kozaric A; Besic L; Mehinovic L; Hasic A; Kozaric M; Hukic M; Marjanovic D
[Ad] Endereço:Department of Genetics and Bioengineering, International Burch University, Francuske revolucije bb, Ilidza, 71210 Sarajevo, Bosnia and Herzegovina.
[Ti] Título:Chemical toxicity and radioactivity of depleted uranium: The evidence from in vivo and in vitro studies.
[So] Source:Environ Res;156:665-673, 2017 07.
[Is] ISSN:1096-0953
[Cp] País de publicação:Netherlands
[La] Idioma:eng
[Ab] Resumo:The main aim of this review is to summarize and discuss the current state of knowledge on chemical toxicity and radioactivity of depleted uranium (DU) and their effect on living systems and cell lines. This was done by presenting a summary of previous investigations conducted on different mammalian body systems and cell cultures in terms of potential changes caused by either chemical toxicity or radioactivity of DU. In addition, the authors aimed to point out the limitations of those studies and possible future directions. The majority of both in vitro and in vivo studies performed using animal models regarding possible effects caused by acute or chronic DU exposure has been reviewed. Furthermore, exposure time and dose, DU particle solubility, and uranium isotopes as factors affecting the extent of DU effects have been discussed. Special attention has been dedicated to chromosomal aberrations, DNA damage and DNA breaks, as well as micronuclei formation and epigenetic changes, as DU has recently been considered a possible causative factor of all these processes. Therefore, this approach might represent a novel area of study of DU-related irradiation effects on health. Since different studies offer contradictory results, the main aim of this review is to summarize and briefly discuss previously obtained results in order to identify the current opinion on DU toxicity and radioactivity effects in relation to exposure type and duration, as well as DU properties.
[Mh] Termos MeSH primário: Poluentes Ambientais/toxicidade
Urânio/toxicidade
[Mh] Termos MeSH secundário: Animais
Aberrações Cromossômicas
Dano ao DNA
Metilação de DNA
Epigênese Genética
Seres Humanos
Radioatividade
[Pt] Tipo de publicação:JOURNAL ARTICLE; REVIEW
[Nm] Nome de substância:
0 (Environmental Pollutants); 4OC371KSTK (Uranium)
[Em] Mês de entrada:1706
[Cu] Atualização por classe:171119
[Lr] Data última revisão:
171119
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170505
[St] Status:MEDLINE


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[PMID]:28441285
[Au] Autor:Ghosh VJ; Schaefer C; Kahnhauser H
[Ad] Endereço:*Energy Sciences Directorate, National Synchrotron Light Source II, Brookhaven National Laboratory, Upton, NY 11973-5000; † Environment Safety and Health Directorate, Radiological Control Division, Brookhaven National Laboratory, Upton, NY 11973-5000.
[Ti] Título:Induced Radioactivity in Lead Shielding at the National Synchrotron Light Source.
[So] Source:Health Phys;112(6):533-543, 2017 Jun.
[Is] ISSN:1538-5159
[Cp] País de publicação:United States
[La] Idioma:eng
[Ab] Resumo:The National Synchrotron Light Source (NSLS) at Brookhaven National Laboratory was shut down in September 2014. Lead bricks used as radiological shadow shielding within the accelerator were exposed to stray radiation fields during normal operations. The FLUKA code, a fully integrated Monte Carlo simulation package for the interaction and transport of particles and nuclei in matter, was used to estimate induced radioactivity in this shielding and stainless steel beam pipe from known beam losses. The FLUKA output was processed using MICROSHIELD® to estimate on-contact exposure rates with individually exposed bricks to help design and optimize the radiological survey process. This entire process can be modeled using FLUKA, but use of MICROSHIELD® as a secondary method was chosen because of the project's resource constraints. Due to the compressed schedule and lack of shielding configuration data, simple FLUKA models were developed. FLUKA activity estimates for stainless steel were compared with sampling data to validate results, which show that simple FLUKA models and irradiation geometries can be used to predict radioactivity inventories accurately in exposed materials. During decommissioning 0.1% of the lead bricks were found to have measurable levels of induced radioactivity. Post-processing with MICROSHIELD® provides an acceptable secondary method of estimating residual exposure rates.
[Mh] Termos MeSH primário: Chumbo/efeitos da radiação
Proteção Radiológica
Radioatividade
Síncrotrons
[Mh] Termos MeSH secundário: Radioisótopos de Chumbo
Método de Monte Carlo
Proteção Radiológica/métodos
Síncrotrons/estatística & dados numéricos
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Lead Radioisotopes); 2P299V784P (Lead)
[Em] Mês de entrada:1707
[Cu] Atualização por classe:170721
[Lr] Data última revisão:
170721
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170426
[St] Status:MEDLINE
[do] DOI:10.1097/HP.0000000000000651


  10 / 1244 MEDLINE  
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[PMID]:28431375
[Au] Autor:Jodlowski P; Macuda J; Nowak J; Nguyen Dinh C
[Ad] Endereço:AGH University of Science and Technology, Faculty of Physics and Applied Computer Science, Al. Mickiewicza 30, 30-059 Kraków, Poland.
[Ti] Título:Radioactivity in wastes generated from shale gas exploration and production - North-Eastern Poland.
[So] Source:J Environ Radioact;175-176:34-38, 2017 Sep.
[Is] ISSN:1879-1700
[Cp] País de publicação:England
[La] Idioma:eng
[Ab] Resumo:In the present study, the K-40, U-238, Ra-226, Pb-210, Ra-228 and Th-228 activity concentrations were measured in 64 samples of wastes generated from shale gas exploration in North-Eastern Poland. The measured samples consist of drill cuttings, solid phase of waste drilling muds, fracking fluids, return fracking fluids and waste proppants. The measured activity concentrations in solid samples vary in a wide range from 116 to around 1100 Bq/kg for K-40, from 14 to 393 Bq/kg for U-238, from 15 to 415 Bq/kg for Ra-226, from 12 to 391 Bq/kg for Pb-210, from a few Bq/kg to 516 Bq/kg for Ra-228 and from a few Bq/kg to 515 Bq/kg for Th-228. Excluding the waste proppants, the measured activity concentrations in solid samples oscillate around their worldwide average values in soil. In the case of the waste proppants, the activity concentrations of radionuclides from uranium and thorium decay series are significantly elevated and equal to several hundreds of Bq/kg but it is connected with the mineralogical composition of proppants. The significant enhancement of Ra-226 and Ra-228 activity concentrations after fracking process was observed in the case of return fracking fluids, but the radium isotopes content in these fluids is comparable with that in waste waters from copper and coal mines in Poland.
[Mh] Termos MeSH primário: Resíduos Industriais/análise
Monitoramento de Radiação
Resíduos Radioativos/análise
Radioatividade
Poluentes Radioativos do Solo/análise
[Mh] Termos MeSH secundário: Gás Natural
Campos de Petróleo e Gás
Indústria de Petróleo e Gás
Polônia
[Pt] Tipo de publicação:JOURNAL ARTICLE
[Nm] Nome de substância:
0 (Industrial Waste); 0 (Natural Gas); 0 (Radioactive Waste); 0 (Soil Pollutants, Radioactive)
[Em] Mês de entrada:1706
[Cu] Atualização por classe:170622
[Lr] Data última revisão:
170622
[Sb] Subgrupo de revista:IM
[Da] Data de entrada para processamento:170422
[St] Status:MEDLINE



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