Ademir Xavier da Silva

Instituição:

Universidade Federal do Rio de Janeiro

Centro:

Centro de Tecnologia

Unidade:

Escola Politécnica

Departamento:

Departamento de Engenharia Nuclear/Poli

ORCID:

não disponível no Lattes


Formação:

  • Universidade Federal do Rio de Janeiro

    Engenharia Nuclear | Doutorado | 1994 - 1999

  • Universidade Federal Fluminense

    Física | Mestrado | 1992 - 1994

  • Universidade Federal Fluminense

    Bacharel em Física | Graduação | 1987 - 1991
Laboratórios:
Nenhum laboratório cadastrado
Nuvens de Palavras:
Artigos:

(66.44% artigos com DOI)

Titulo DOI Ano
Internal dose rate due to intake of uranium and thorium by fish from a dam reservoir associated with a uranium mine in Brazil 10.1007/s00411-023-01051-2 2024
Environmental impact assessment due to the intake of uranium contained in surface waters in a semi-arid region in Brazil 10.1007/s11356-024-32671-w 2024
Assessment of radiological hazards from radioactivity natural of cement used in Dwellings in Rio de Janeiro, Brazil 10.1016/j.apradiso.2024.111266 2024
Assessment and estimation of the effective dose due to external exposure from natural radioactivity of sands used in civil construction in the state of Rio de Janeiro,Brazil 10.1016/j.apradiso.2023.111157 2024
Application of radiological assessment as water quality criterion for effluent release in a Brazilian uranium mine 10.1007/s11356-023-26964-9 2023
Potential increased radiological risk in cargo scanning activity 10.1051/radiopro/2022040 2023
Investigation of Rhodnius prolixus head anatomy using microtomography 10.1111/jmi.13186 2023
Application of deep neural network and gamma radiation to monitor the transport of petroleum by-products through polyducts 10.1016/j.apradiso.2023.110973 2023
Void fraction prediction using prompt gamma neutron activation analysis and artificial intelligence 10.1016/j.radphyschem.2023.111212 2023
Excess lifetime cancer risk due to ingestion of fish from a dam reservoir associated with a nuclear facility in Brazil 10.1016/j.apradiso.2023.111033 2023
Radiometric analysis of Brazilian commercial ornamental stones 10.1016/j.apradiso.2023.111020 2023
Determinação de curvas de eficiência para análise de presença de radionuclídeos em frutas orgânicas através de espectrometria gama utilizando detector HPGe 10.55905/revconv.16n.12-255 2023
Assessment of released natural radionuclides by waste rock pile and mining pit associated with a uranium mine at Caldas, Minas Gerais, Brazil 10.1007/s11356-022-19887-4 2022
Intake of natural radionuclides present in organic and conventional foods: radiological aspects 10.1007/s10967-021-08162-4 2022
Fast radiological safety evaluation applied to maintenance in cargo and container inspection facilities 10.1177/07482337221080801 2022
Evaluation of the radiological risk in cargo scanning by comparison with known biological consequences 10.1051/radiopro/2021036 2022
Dose conversion coefficients to marine biota due to natural radionuclides in an oil spill accident using Monte Carlo simulation 10.1590/0001-3765202220210303 2022
Absorbed dose rate for marine biota due to the oil spilled using ICRP reference animal and Monte Carlo simulation 10.1016/j.apradiso.2022.110354 2022
Experimental and simulated methods to characterize the response of a scintillator detector 10.1016/j.radphyschem.2021.109895 2022
Identification of the interface region in transport of petroleum by-products in polyducts using artificial neural network and gamma densitometry by the MCNPX code 10.1016/j.radphyschem.2021.109908 2022
Use of gamma radiation and artificial neural network techniques to monitor characteristics of polyduct transport of petroleum by-products 10.1016/j.apradiso.2022.110267 2022
Relationships between natural radionuclides activity concentration in soils of the State of Alagoas, Brazil and WRB/FAO soil classification, types of parental rocks and rainfall variability 10.1016/j.apradiso.2022.110309 2022
Evaluating urban resilience in a disruptive radioactive event 10.1016/j.pnucene.2022.104218 2022
S-Values for Radium-223 and absorbed doses estimates for 223RACL2 using three computational phantoms 10.1016/j.apradiso.2022.110387 2022
An assessment of committed effective dose and lifetime cancer risk due to the ingestion of infant milk 10.1016/j.apradiso.2022.110468 2022
137Cs activity concentration in soil of Alagoas State, Brazil. 10.1016/j.apradiso.2021.109607 2021
Occupational monitoring at radioactive waste deposit 10.15392/bjrs.v8i3B.509 2021
A modeled radiological dispersive device release and the impact to decision-making in an urban environment 10.2298/NTRP2004316O 2021
Electrochemical method for production of bromine-82 radiotracer in organic phase for use in oil industry 10.1007/s10967-020-07529-3 2021
Committed effective dose and lifetime cancer risk due to ingestion of natural radionuclides in grains grown in an area of high background radiation 10.1016/j.apradiso.2021.109656 2021
131I and 99mTc in Effluents from a Nuclear Medicine Facility and Associated Sewage Treatment Unit 10.1007/s11270-021-05076-5 2021
Volume fractions calculation of a biphasic system on cylindrical tube using gamma ray and MCNP6 code 10.15392/bjrs.v9i1A.1388 2021
Monitoring of atmospheric emission of alpha emitters radionuclides at a nuclear fuel cycle facility in RJ, Brazil 10.15392/bjrs.v9i1A.1559 2021
Radiological urban threat due to special protective actions from security forces 10.1177/15485129211016539 2021
Impact of the affected population size assessment on the decision-making after a nuclear event 10.1016/j.apradiso.2021.109907 2021
Lifetime cancer risk increase due to consumption of some foods from a High Background Radiation Area 10.1016/j.apradiso.2021.109855 2021
SYSTEM TO DETECT THE INTERFACE REGION AND IDENTIFY PRODUCTS TRANSPORTED BY POLYDUCTS USING ARTIFICIAL INTELLIGENCE AND GAMMA RADIATION THROUGH MCNP6 CODE 10.1016/j.measurement.2021.110093 2021
Radiological quality of wastewater released from a waste dam containing natural radionuclides 10.1007/s10967-021-07973-9 2021
MCNPX computational modeling applied to the potential dose rates calculation of cargo scanning 10.1016/j.apradiso.2021.109967 2021
Activity concentration and mapping of radionuclides in Espírito Santo State soils, Brazil 10.1016/j.radphyschem.2019.03.013 2020
Baseline, mapping and dose estimation of natural radioactivity in soils of the Brazilian state of Alagoas 10.1016/j.radphyschem.2019.05.022 2020
Committed effective dose due to consumption of fruits and vegetables peels: Analysis on cancer risk increase 10.1016/j.radphyschem.2019.03.047 2020
Evaluation of cancer risk after a release from a hypothetical nuclear reactor steam generator tube rupture accident (SGTR) 10.1016/j.anucene.2019.107023 2020
Dose distribution in boron neutron capture therapy for the treatment of brain cancer 10.1016/j.radphyschem.2019.108611 2020
Flow regime and volume fraction identification using nuclear techniques, artificial neural networks and computational fluid dynamics 10.1016/j.apradiso.2020.109103 2020
Study on radiation dosimetry and radioprotection applied to Seaport Cargo Inspection Activity 10.1016/j.apradiso.2020.109130 2020
Monitoring system of oil by-products interface in pipelines using the gamma radiation attenuation 10.1016/j.apradiso.2020.109125 2020
Preclinical radiation internal dosimetry in the development of new radiopharmaceuticals using GATE Monte Carlo simulation 10.1016/j.radphyschem.2020.108879 2020
Individual dose planning in radiosynoviorthesis treatment: Step by step 10.1016/j.apradiso.2020.109177 2020
Shielding implications on secondary radiation doses in prostate cancer treatment 10.1016/j.apradiso.2020.109163 2020
Radiation-induced cancer risk and decision-making in a simulated Cs-137 urban event 10.2478/nuka-2020-0005 2020
Comparison between codes MCNPX and Gate/Geant4 in volume fraction studies 10.1016/j.apradiso.2020.109226 2020
Radiological evaluation of Ra-226, Ra-228 and K-40 in tea samples: A comparative study of effective dose and cancer risk 10.1016/j.apradiso.2020.109326 2020
Modeling of a neutron irradiator using Monte Carlo 10.1016/j.apradiso.2020.109332 2020
Urban critical infrastructure disruption after a radiological dispersive device event 10.1016/j.jenvrad.2020.106358 2020
Evaluation of the radiological quality of water released by a uranium mining in Brazil 10.1007/s11356-020-09672-6 2020
Radioactive gold nanocluster (198-AuNCs) showed inhibitory effects on cancer cells lines 10.1080/21691401.2020.1821698 2020
Brazilian regulatory authority contribution to the shielding dimensioning model of radiotherapy rooms proposed by the NCRP 151 10.1088/2057-1976/abbabe 2020
SPECT performance evaluation on image of Yttrium 90 - Bremsstrahlung using Monte Carlo simulation 10.1016/j.apradiso.2020.109456 2020
Determinação dos níveis de radioatividade natural em amostras de solo do Núcleo Piraquara ? Parque Estadual da Pedra Branca 10.17648/uezo-ast-v8i2.294 2020
Radioactive particle tracking methodology to evaluate concrete mixer using MCNPX code 10.1016/j.radphyschem.2019.03.027 2019
Dose rate in a deactivated uranium mine 2019
The vertical radiation dose profile and decision-making in a simulated urban event 10.1016/j.jenvrad.2019.106034 2019
Taxa de dose absorvida no ar devido ao radionuclídeo 40K presente em amostras de rochas do Núcleo Piraquara - Parque Estadual da Pedra Branca 2019
Selective contribution of concrete shielding on the equivalent and effective doses in a prostate radiotherapy treatment 10.1051/radiopro/2017041 2018
COMMITTED EFFECTIVE DOSE DUE TO THE INTAKE OF 40K, 226Ra, 228Ra AND 228Th CONTAINED IN FOODS INCLUDED IN THE DIET OF THE RIO DE JANEIRO CITY POPULATION, BRAZIL 10.1093/rpd/ncx310 2018
Determination of Ra-226, Ra-228 and K-40 specific activities in samples of mineral fertilizers marketed in the city of Rio de Janeiro, Brazil 10.1016/j.apradiso.2018.04.013 2018
Comparison of simulated and experimental values of self-absorption correction factors for a fast and credible adjust in efficiency curve of gamma spectroscopy 10.1016/j.apradiso.2018.05.005 2018
Evaluation of collimator rotation for volumetric modulated arc therapy lung stereotactic body radiation therapy using flattening filter free 10.1016/j.apradiso.2018.05.026 2018
Monte Carlo simulation for the treatment of male breast cancer 2018
Modelagem computacional do laboratório de instrumentação e de detecção nuclear do Instituto Militar de Engenharia 10.18605/2175-7275/cereus.v10n2p137-141 2018
Equivalent dose calculation in simulation of lung cancer treatment and analysis of dose distribution profile 10.1016/j.apradiso.2018.07.012 2018
Study of K-40, Ra-226, Ra-228 and Ra-224 activity concentrations in some seasoning and nuts obtained in Rio de Janeiro city 2018
COMPARISON OF THE NEUTRON ENERGY RESPONSE OF TWO DIFFERENT TLD ALBEDO DOSEMETERS 10.1093/rpd/ncx256 2018
Evaluation of equivalent and effective dose by KAP for patient and orthopedic surgeon in vertebral compression fracture surgery 10.1016/j.radphyschem.2016.11.011 2017
A New Approach for Radiosynoviorthesis: A Dose-Optimized Planning method Based on Monte Carlo Simulation and Synovial Measurement Using 3D Slicer and MRI 10.1002/mp.12276 2017
Cancer risk coefficient for patient undergoing kyphoplasty surgery using Monte Carlo Method 10.1016/j.radphyschem.2017.02.024 2017
Dosimetry in Radiosynoviorthesis 10.1097/hp.0000000000000730 2017
Assessment of uranium release to the environment from a disabled uranium mine in Brazil 10.1016/j.jenvrad.2017.11.012 2017
The State of the Art of the World Radioprotection System 2017
SIMULAÇÃO DE UM DETECTOR FLAT PANEL UTILIZANDO O CÓDIGO DE MONTE CARLO MCNPX 2017
MCNP SIMULATION OF THE (10) ENERGY RESPONSE OF A BRAZILIAN TLD ALBEDO NEUTRON INDIVIDUAL DOSEMETER, FROM THERMAL TO 20 MeV 10.1093/rpd/ncv379 2016
Proposed management and exemption of radioactive waste in nuclear medicine facilities according to the recommendations of the ICRP Publication 103 2016
Generation of Dose Volume Histograms Using Voxel Structure and the Monte Carlo Method in Low Dose Rate Brachytherapy 10.4236/ijmpcero.2016.54024 2016
Comparison of the effective dose rate to aircrew members using hybrid computational phantoms in standing and sitting postures 10.1088/0952-4746/36/4/885 2016
Evaluation of the Radiotherapy Treatment Planning in the Presence of a Magnetic Valve Tissue Expander 10.1371/journal.pone.0117548 2015
Effect of external shielding for neutrons during radiotherapy for prostate cancer, considering the 2300 cd linear accelerator and voxel phantom 10.1016/j.radphyschem.2013.02.013 2014
Dose Conversion Coefficients for Icrp110 Voxel Phantom in the Geant4 Monte Carlo Code 10.1016/j.radphyschem.2013.04.030 2014
Analysis of the Influence of Liquid and of External Coating Material on the Quality of the Radiographic Image of Offshore Pipes using Computational Modeling 10.4028/www.scientific.net/MSF.775-776.197 2014
Simulation of Siemens ONCOR- Expression linear accelerator using phase space in the MCNPX code 10.1016/j.pnucene.2013.07.013 2014
Using computational modeling to compare X-ray tube Practical Peak Voltage for Dental Radiology 10.1016/j.radphyschem.2013.05.037 2014
Computational system to create an entry file for replicating I-125 seeds simulating brachytherapy case studies using the MCNPX code 10.14319/ijcto.0202.3 2014
PEDS: Software to Assess Wall Thickness Loss and Weld Thickness Loss in Offshore Pipelines Through Digital Radiography 2014
Influence of the Presence of Tissue Expanders on Energy Deposition for Post-Mastectomy Radiotherapy 10.1371/journal.pone.0055430 2013
Gafchromic EBT2 dosimetry via robust optimization 10.1016/j.cpc.2013.02.023 2013
Calculation of Dose in Healthy Organs, during Radiotherapy 4-Field Box 3D Conformal for Prostate Cancer, Simulation of the Linac 2300, Radiotherapy Room and MAX Phantom 10.4236/ijmpcero.2013.22009 2013
Application of digital image processing for the generation of voxels phantoms for Monte Carlo simulation 2012
Dose optimization in 125I permanent prostate seed implants using the Monte Carlo metrhod 2012
Calculation of conversion coefficients for air kerma to ambient dose equivalent using transmitted spectra of megavoltage X-rays through concrete 10.1093/rpd/ncs070 2012
Characterization of a two component thermoluminescente albedo dosemeter according to ISSO 21909 2011
Development of a shielding to protect patients against photoneutrons produced by linacs in radiotherapy treatments 2011
Evaluation of the dose and of the risk of cancer induction associated with the use of transmission X-ray body scanners using the Monte Carlo MCNPX code 2011
Monte Carlo simulation of photoneutrons streaming inside radiotherapy treatment rooms as a function of gantry angles 2010
Diagnostic assessment to estimate and minimize neutron dose rates received by occupationally exposed individuals at cyclotron facilities 2010
Computed Radiography Simulation using the Monte Carlo Code MCNPX 10.1016/j.apradiso.2010.02.011 2010
Photon doses at the entrance of Co-60 and low-energy medical accelerators rooms under unusual irradiation conditions 10.1093/rpd/ncp245 2010
Detection of drugs and explosives using Neutron Computerized Tomography and Artificial Intelligence Techniques 10.1016/j.apradiso.2010.01.019 2010
Electronic Imaging System for Neutron Radiography at a Low Power Research Reactor 2010
Dose and risk evaluation in thoracic radiology using male and female voxel phantoms 10.1504/IJLR.2010.032812 2010
Alternative irradiation system for efficiency manganese bath determination 2010
Brazilian two-component TLD albedo neutron individual monitoring system 2010
Study of the Influence of Casing and Liquid inside Oil Wells on the Response of Neutron Logging Tools 2010
Estudo da atenuação do feixe de 6 MV em tratamentos radioterápicos de mama pós-mastectomia devido à heterogeneidade metálica de expansores de tecido 2010
Spectrally average conversion coefficients for air kerma to ambient dose equivalent for clinical linear accelerator 2009
Use of a voxel phantom as a source and a second voxel phantom as a target to calculate effective doses in individuals exposed to patients treated with 131I 10.2967/jnmt.108.058172 2009
Assessment of weld thickness loss in offshore pipelines using computed radiography and computational modeling 10.1016/j.apradiso.2009.05.015 2009
Prediction of volume fractions in three-phase flows using nuclear technique and artificial neural network 10.1016/j.apradiso.2009.02.093 2009
Multileaf shielding design against neutrons produced by medical linear accelerators 10.1093/rpd/ncm312 2008
Use of a bioindicator system in the study of the mutagenetical effects in the neighborhoods of deposits of radioactive waste 2008
Methodology for digital radiography simulation using the Monte Carlo code MCNPX for industrial applications 2008
Dose image quality study in digital chest radiography using Monte Carlo simulation 10.1016/j.apradiso.2008.01.009 2008
AP and PA thorax radiographs: dose evaluation using the FAX phantom 2008
On the production of neutrons in laminated barriers for 10 MV medical accelerator rooms 2008
Neutron scattering in concrete and wood: part II - oblique incidence 2008
Monte Carlo simulation of scattered and thermal photoneutron fluences inside a radiotherapy room 2007
Neutron dose calculation at the maze entrance of medical linear accelerator rooms 2007
The use of high-density concretes in radiotherapy treatment room design 2007
Study of the use of thermoluminescent materials in mixed fields 2007
Neutron Scattering in Concrete and Wood 10.1093/rpd/ncl144 2006
A study of neutron spectra from medical linerar accelerators 2005
Desenvolvimento de um Sistema Eletrônico para Obtenção de Imagens Radiográficas com Nêutrons em Tempo Real 2005
Desenvolvimento de uma matriz resposta para o espectrômetro de multiesferas de bonner 2005
Monte Carlo Simulation of Response Functions for NaI(Tl) Detector for Gamma Rays from of 241Am-Be Source 2005
Neutron Dose Rate Evaluation for Medical Linear Accelerators 2004
Calculation of Conversion Coefficients for Photon Spectra Clinical Using the MCNP code 2004
Implantação de um Sistema Eletrônico para Aquisição de Imagens Neutrongráficas em Tempo Real no Reator Argonauta do IEN/CNEN 2004
Calculation of Dose Components in Head Phantom for Boron Neutron Capture Therapy 2003
Explosives detection using prompt-gamma neutron activation and neural networks 2002
Neutron Tomography using Projection Data Obtained by Monte Carlo Simulation for Nondestructive Evaluation 2002
Dependência Angular de Dosímetros Termoluminescentes Utilizados em Tomografia Computadorizada 2002
Verificação da Viabilidade da Detecção de Virions, através da Análise por Ativação com Nêutrons 2002
Cálculo dos Fatores de Conversão de Kerma no Ar para Equivalente de Dose Ambiental para Feixes Monoenergético de Fótons entre 0,01 MeV e 50 MeV 2002
Moderator-Collimator-Shielding Design for Neutron Radiography Systems Using 252Cf 2001
A Study of a Neutron Radiography System Using 252Cf Neutron Source 2001
Shielding Design Studies for a Neutron Irradiator System Based on a 252Cf Source 2001
Use of Thermal Neutron Tomography for the Detection of Drugs and Explosives 2001
Neutrongrafia Aplicada no Combate ao Narcotráfico e ao Terrorismo 1999
Studies of Isochronal and Isothermal Annealing of Alpha Particle Tracks in CR-39 Polymer Detectors 1996
Thermal Annealing of Proton Tracks With Energies of 4 and 6 MeV in CR-39 Polymer Detectors 1994
Eventos:

(0.00% eventos com DOI)

Titulo DOI Ano
Monitoring of Atmospheric Emission of Alpha Emittters Radionuclides at a Nuclear Fuel Cycle Facility in RJ, Brazil 2019
Natural uranium in biological material from high background radiation areas in Brazil 2018
Evaluation of equivalent dose due photons and neutrons during radiotherapy of lung cance 2018
Radioactive particle tracking methodology to evaluate concrete mixer using MCNPX code 2018
Activity concentration of Ra-226, Ra-228 and K-40 in different types of teas raw samples 2018
Commited effective dose due to fruits and vegetables peels consumption: a radiometric analysis of the low-cost dietary nutritional alternative 2018
NATURAL RADIONUCLIDES IN EFFLUENTS RELEASE BY A DEACTIVATED URANIUM MINE 2017
DOSE RATE IN A DEACTIVATED URANIUM MINE. 2017
OCCUPATIONAL MONITORING AT RADIOACTIVE WASTE DEPOSIT 2017
Committed effective dose due to the intake of 40K, 226Ra, 228Ra and 228Th contained in foods included in the diet of the population of the city of Rio de Janeiro, Brazil 2017
Simulation of lung cancer treatment with equivalent dose calculation and analysis of the dose distribution profile 2017
Determination of Ra-226, Ra-228 and K-40 specific activities in samples of mineral fertilizer used in the Brazilian city of Rio de Janeiro 2017
DETERMINATION OF THE SPECIFIC ACTIVITIES OF RA-226, RA-228 AND K-40 IN SAMPLES OF MINERAL NITROGEN, POTASSIUM AND PHOSPHATE FERTILIZERS 2016
DETERMINATION OF RA-226, RA-228 AND E K-40 SPECIFIC ACTIVITIES IN SAMPLES OF MINERAL NPK COMPOUND FERTILIZER 2016
Natural uranium in biological material from high natural radioactivity areas in Brazil 2016
Ore transportation with Naturally Occurring Radioactive Materials-in Braz 2016
Risk assessment as justification for transporting empty packaging as excepted package 2016
A comparison of the Brazilian rule for the transport radioactive material with the IAEA Regulations for the Safe Transport of Radioactive Material 2012. 2016
ESCOLHA DE LOCAIS CRÍTICOS SOB O PONTO DE VISTA DE RADIOPROTEÇÃO VISANDO À REDUÇÃO DAS DOSES: OTIMIZAÇÃO DA RADIOPROTEÇÃO EM INSTALAÇÃO NUCLEAR 2016
COMPARISON BETWEEN BRAZILIAN RADIATION PROTECTION NORM AND THE IAEA BASIC SAFETY SATANDART PUBLISHED IN 2014 2016
The principle of low risk and optimization and the connection with the ALARA concept. Exemption, exclusion and clearance 2016
Licensing of nuclear facilities in Brazil: Radiological aspects 2016
THE STATE OF THE ART ABOUT THE RADIATION PROTECTION SYSTEM IN THE WORD 2016
Determination of specific concentrations of 40K, 238U and 232Th in mineral fertilizer samples. 2015
COMPARISON BETWEEN STEEL AND LEAD SHIELDINGS FOR RADIOTHERAPY ROOMS REGARDING NEUTRON DOSES TO PATIENTS 2015
RELATIVE EFFICIENCY CALCULATION OF A HPGe DETECTOR USING MCNPX CODE 2015
ALCULATION OF ISODOSE CURVES FROM INITIAL NEUTRON RADIATION OF A HYPOTHETICAL NUCLEAR EXPLOSION USING MONTE CARLO METHOD 2015
Gamma ray densitometry techniques for measuring of volume fractions. 2015
Underwater gamma-ray NaI(Tl) detector using MCNP-X. 2015
RADIONUCLÍDEOS EM ÁGUAS EM UMA REGIÃO DE ALTA RADIOATIVIDADE NATURAL 2015
URÂNIO EM ÁGUA NUMA REGIÃO DE ALTA RADIOATIVIDADE NO BRASIL 2015
URÂNIO EM MATERIAL BIOLÓGICO I: URÂNIO NA BAHIA, BRASIL. 2015
URÂNIO EM MATERIAL BIOLÓGICO II: URÂNIO NO CEARÁ, BRASIL. 2015
URÂNIO EM MATERIAL BIOLÓGICO III. URÂNIO EM MINAS GERAIS 2015
TÓRIO EM MATERIAL BIOLÓGICO I: TÓRIO NA BAHIA, BRASIL 2015
TÓRIO EM MATERIAL BIOLÓGICO II: TÓRIO NO CEARÁ, BRASIL. 2015
TÓRIO EM MATERIAL BIOLÓGICO III. TÓRIO EM MINAS GERAIS, BRASIL 2015
ENVIRONMENTAL RADIOLOGICAL IMPACT OF A BRAZILIAN DEACTIVATED URANIUM MINE ALONG THE PERIOD 1999-2009. 2015
CÁLCULO DE DOSE DEVIDO A INGESTÃO DE 40K CONTIDO EM AMOSTRAS DE FEIJÃO UTILIZANDO ESPECTROMETRIA GAMA E SIMULAÇÃO DE MONTE CARLO 2014
Monitor unit calculation for radiotherapy treatments using the Monte Carlo method 2014
CÁLCULO GAMA ESPECTRAL NO INTERIOR DO IRRADIADOR DE PESQUISA DO CENTRO TECNOLÓGICO DO EXÉRCITO UTILIZANDO O CÓDIGO MCNPX E COMPARAÇÃO COM ESPECTROS DE ENEGIA DO CÉSIO 137 LEVANTADOS EM LABORATÓRIO 2013
CÁLCULO DAS TAXAS DE DOSE NO CANAL DE FUGA DO IRRADIADOR GAMA DE PESQUISA DO CENTRO TECNOLÓGICO DO EXÉRCITO UTILIZANDO O CÓDIGO MCNPX 2013
SHIELDING OF A ROOM FOR INSTALLATION OF A CALIBRATION SERVICE FOR NEUTRON MONITORS 2013
Monte Carlo Simulation for the Production of Neutrons Inside the Labyrinth Function Rooms Radiotherapy in Head Rotation of Medical Linear Accelerator Use and Energy Operation 2013
MCNPX CALCULATIONS OF DOSE RATES AND SPECTRA IN EXPERIMENTAL CHANNELS OF THE CTEx IRRADIATING FACILITY 2013
Cálculo dos coeficientes de conversão do equivalente de dose pessoal e fatores de retroespalhamento em radiologia diagnóstica 2012
Sistema computacional de posicionamento virtual de grade em estruturas lattice para a inserção de sementes de 125I de 103Pd para aplicação no tratamento de prostata 2012
Software to assess wall thickness loss and weld thickness loss in offshore pipelines through Digital Radiography 2012
Análise da Influência de líquido e de Material de Revestimento Externo na Qualidade da Imagem Radiográfica de Dutos Offshore Através de Modelagem Computacional 2012
SIMULATION OF DOSE RATE DISTRIBUTIONS IN THE RESEARCH IRRADIATING FACILITY AT CTEx WITH THE MCNPX COMPUTER CODE 2012
MCNPx SIMULATION OF GAMMA RAY SCATTERING IN THE CTEx RESEARCH IRRADIATING FACILITY 2012
MCNPX MODELLING OF A LOW- ‐DOSE LEAD ASSEMBLY IN THE CTEX RESEARCH IRRADIATING FACILITY 2012
CALCULATION OF THE LINEAR ACCELERATOR PDP VARIAN 2300C / D, OPERATING AT 10, 15 and 18 MV BY MONTE CARLO SIMULATION USING MCNPX CODE. 2012
CALCULATION OF HEALTHY ORGAN DOSE DUE PHOTONS AND NEUTRONS FOR PATIENTS UNDERGOING PROSTATE RADIOTHERAPY WITH 15 MV X- ‐RAY BEAM USING COMPUTER MODELING AND VOXEL PHANTOM 2012
CALCULATIONS OF A LOW ENRICHED URANIUM DIOXIDE BENCHMARK EXPERIMENT USING MCNPX AND SCALE V. In: 12th International Symposium on Radiation Physics 2012
Cálculo da dose equivalente e efetiva proveniente de fótons em órgãos sadios num tratamento radioterápico de próstata utilizando modelagem computacional e fantoma em voxel 2012
Avaliação da Dose e do Risco de Indução ao Câncer associados ao uso de Escâneres Corporais de Raios X por Transmissão em Aeroportos 2011
Estimativa da dose e risco de indução ao câncer em operadores durante procedimentos de perfilagem de poços de petróleo com sondas wireless nucleares através de modelagem computacional 2011
Development of s Shielding to Protect Patients Against Photoneutrons Preoduced by LINACS in Radiotherapy Treatments 2011
Isodose curve determination of prostate for the tretment of brachytherapy using MCNPX code 2011
Computer software to assess weld thickness loss in offshohe pipelines: PEDS 2010
Simulation of density curve for slim brorehole using the Monte Carlo Code MCNPX 2010
Dose and risk evaluation in digital mammography using computer modelling 2010
Estudo da Influencia do Revestimento e Liquido no Interior de Poços de Petróleo na Resposta de Ferramentas Neutrônicas de Perfilagem 2010
Cálculo de Dose em Órgão Sadios, devido a Fótons, no Tratamento de Radioterapia para Câncer de Próstata, utilizando Modelagem Computacional e o Fantoma em Voxel 2010
Determinação de Coeficientes de Conversão de Dose Efetiva em Exames Radiográficos Neonatais de Tórax usando Modelagem Computacional 2010
Análise do Efeito da Radiação Espalhada na obtenção de Imagens Radiográficas Digitais de Dutos Offshore através de Modelagem Computacional 2010
Calibration of x-rays tubes in practical peak voltage using computational modeling 2010
Análise, usando o código MCNPX, do efeito de uma blindagem contra nêutrons para aceleradores lineares usados em radioterapia, considerando a rotação do gantry do acelerador 2010
Desenvolvimento de uma blindagem contra fotonêutrons para proteção de pacientes submetidos à radioterapia.. In: XIII Encontro de Modelagem Computacional 2010
Comparação da simulação computacional da fonte de braquiterapia de iodo-125 Amersham 6711 usando os códigos de Monte Carlo Geant$ e MCNPX 2010
Calculation of Decrease in the Prostate Dose Due to Post-Surgical Edema and Heterogeneity in Prostate Brachytherapy 2010
Prostate Dose Calculations for Permanent Implants using the MCNPX Code and the Voxels Phantom MAX 2010
Evaluation of transmitted espectra of megavoltage X rays through concrete using Monte Carlo simulation 2010
Cálculo de dose em exame de escoliose utilizando simuladores antropomórfico de voxel 2009
Computed Radiography Simulation Using the Monte Carlo Code MCNPX 2009
Avaliação da blindagem intersementes na braquiterapia de próstata usando o codigo MCNPX 2009
Optimization of Digital Chest Radiography Using Computer Modeling and Voxels Phantoms 2009
Simulation Of the 3He(n-p) Reaction for Nuclear Well Logging Applications 2009
3He(n,p) Reaction Simulation for Formation Analyses 2009
Cálculo de Criticalidade Comparando-se O MCNPX com Método do Albedo 2009
Cálculo de PDP do Acelerador Linear Varian 2300, Operando a 18 MV, Através da Simulação em Monte Carlo Usando O Código MCNP 5. 2009
Proposals couting method for bubble detectors and their intercomparisons 2009
Semi-automatic bubble counting system for superheated droplet detectors 2009
Calculation of conversion coefficients for effective dose for neutrons using a female voxel anthropomorphic model and the MCNPX code 2009
Attenuation factors in terms of air kerma to ambient dose equivalent and effective dose for diagnostic X rays rooms 2009
Artificial neural network and neutron application in a volume fraction calculation in annular and stratified multiphase system 2009
Characterization of Some Dosimetric Parameters of 125I Seeds Used for Prostate Implants using Monte Carlo Simulations 2009
Methodology for converting CT medical images to MCNP input using the Scan2MCNP system 2009
Insertion of the structure of irregular geometries dicom image-making a cell for the simulations in MCNP 2009
A methodology to estimate and minimize neutron dose rates received by occupationally exposed individuals at IEN/CNEN cycloton facilities 2008
Door shielding for low-energy medical accelerators rooms under unusual irradiation conditions 2008
Dose and risk evaluation to the thyroid gland in intra-oral dental radiology 2008
Attenuation factors in terms of air kerma to ambient dose equivalent and effective for diagnostic X rays rooms 2008
Modelagem de detector NaI(Tl) usando MCNP-X 2008
Simulação em Monte Carlo da contaminação de fotonêutrons dentro da sala de radioterapia em função da inclinação do gantry do acelerador linear 2008
Uso de rede neural e técnica nuclear na identificação de frações de volume em fluxo trifásico estratificado 2008
Dose calculated using Monte Carlo code in mixed field 2008
Modelagem e calibração de um sistema de radiografia computadorizada utilizando o código de Monte Carlo MCNP-X 2008
Cálculo de frações de volume em sistema de escoamento anular, tipo PVC/água/gás, utilizando MCNP-X e rede neural 2007
Avaliação da dose na mama em exames radiográficos de tórax usando MCNPX e o fantoma feminino FAX 2007
Programa imagem: um programa de pós-processamento de dados para simulação de imagens radiográficas com o código MCNPX 2007
Análise da resposta do modelo esférico recomendado pela NCRP79 para cabeçotes de equipamentos de radioterapia 2007
Comparison between different methodologies to calculation of dose in thyroid therapy cancer 2007
Effective dose in individuals from exposure the patients treated with 131I using Monte Carlo Method 2007
Calibration of a TLD albedo individual neutron monitor 2007
TLD albedo dosimeter performance on a Hp(10) neutron dose IAEA intercomparison 2007
Gamma ray interaction probability calculation due 56Mn for ultima gold and insta-gel plus liquid scintillators 2007
Detection of drugs and plastic explosives using neutron tomography 2007
Volume fraction calculation in multiphase system such as oil-water-gas using neutron 2007
Study of volume fractions for stratified and annular regime in multiphase flows using gamma-rays and artificial neural network 2007
Comparison of some popular Monte Carlo solutions for proton transportation within pCT problem 2007
Calculation of fluence-to-ambient dose equivalent conversion coefficients for neutron energies between 100 keV and 10 MeV using MCNPX code 2007
Natural radioactivity in environmental samples from Ponta Negra, Maricá (RJ, Brazil) 2007
A new approach for the calculation of average conversion coefficients in the ICRU sphere for diagnostic X ray beams 2007
Calculation of average conversion coefficients for air kerma to effective dose for diagnostic X ray beams 2007
Shielding for neutrons produced by medical linear accelerators 2007
Modeling and analysis of anti-scatter grids for analogical and digital systems using MCPX 2007
Digital radiography simulation for industrial aplications with MCNPX 2007
Primary and scattered component analyses of simulated images with MCNPX 2007
Study of the potentiality application of nuclear techniques and artificial neural network in the determination of volume fractions in multiphase system 2007
The study of the mutagenetical effects of low dose level exposure to ionizing radiation using a bioindicator system close to deposits of radioactive waste 2007
Patient dose study in chest radiographic examinations for different exposure techniques using Monte Carlo methods and voxel phantom 2007
Exames radiográficos de tórax AP e PA: uma avaliação da dose usando o fantoma feminino FAX 2007
Image quality optimitization in digital chest radiography using MCNPX 2006
O emprego de uma blindagem multifolhas para fotonêutrons produzidos por aceleradores lineares de uso médico 2006
Determinação de frações de volume em sistema de escoamento multifásico utilizando atenuação de raios gama e rede neurais 2006
Development of a data post processing program of image simulation with MCNP5 2006
Total reflection X-ray fluorescence spectrometry: A simulated study using the Monte Carlo method 2006
Estudo da utilização de materiais termoluminescentes em campos mistos 2005
Desenvolvimento de um novo sistema eletrônico para obtenção de imagens radiográficas com nêutrons 2005
Aplicação de técnicas de processamento digital de imagens para a caracterização de sistemas eletrônicos de aquisição de imagens de radiografia com nêutrons em tempo real 2005
Cálculo de blindagem para irradiadores de pequeno porte com fontes de 241Am-Be, utilizando o código MCNP-4B 2005
Calculations of effective dose conversion coefficients for photon spectra clinical 2005
Determinação de uma matriz resposta para o espectrômetro de multiesferas de bonner 2005
Skyshine para Fótons:Comparação entre abordagem teória e Simulação pelo Método de Monte Carlo 2005
Simulação de Dose Ocupacionais em Radiografia Industrial 2005
Simulação por Monte Carlo dos Feixes de 6 e 15 MV do Clinac 2100 utilizando o Código MCNP4B 2005
Aspectos Normativos Sobre Ocorrência Natural De Material Radioativo em Rejeitos de Petróleo 2005
Shielding for Photoneutrons Produced in the head of a 18 MV Linear Accelerator 2005
Calculation of Conversion Coefficients from Air Kerma to Ambient Dose Equivalent for Medical Linear Accelerators 2005
Calculation of Photoneutron Dose in Organs using Adult Mathematical Phantom and Monte Carlo Method 2005
The Calculation of Dose from External Photon Exposures using Human Mathematical Phantom and Monte Carlo Method 2004
Calculations of Effective Dose Conversion Coefficients for Photon Spectra Clinical 2004
The Licensing Progress of Fifteen Medical Linear Accelerators in Brasil 2004
Calculation of conversion coefficients H*(10)/kair for photon energies between 10 keV and 50 MeV using MCNP4B 2003
Children and adult dose evaluation in CT using Monte Carlo Method 2003
Development of a neutron radiography system using 241-Am neutron source for industrial applications 2003
Estudo do espectro de neutrons provenientes de aceleradores lineares de uso medico 2003
Neutron fluence evaluation around medical linear accelerators 2003
Calculation of conversion coefficients for photon spectra clinical using MCNP code 2003
VERIFICAÇÃO DA VIABILIDADE DE DETECÇÃO DE VIRIONS ATRAVÉS DA ANÁLISE POR ATIVAÇÃO COM NEUTRONS 2002
CÁLCULOS DOS FATORES DE CONVERSÃO DE KERMA NO AR PARA EQUIVALENTE DE DOSE AMBIENTAL PARA FEIXE MONOENERGÉTICO DE FÓTONS ENTRE 0,01 MeV E 50 MeV . 2002
DEPENDÊNCIA ANGULAR DE DOSÍMETROS TERMOLUMINESCENTES UTILIZADOS EM TOMOGRAFIA COMPUTARIZADA 2002
CALCULATION OF DOSE COMPONENTS IN HEAD PHANTOM FOR BORON NEUTRON CAPTURE THERAPY 2002
CALCULATION OF THE AMBIENTE DOSE EQUIVALENTE, EQUIVALENT DOSE AND DOSE EFFECTIVE DOSE FOR PHOTON SPECTRA FROM MEDICAL LINEAR ACCELERATORS 2002
THE CALCULATION OF AMBIENT DOSE EQUIVALENT, EQUIVALENT DOSE AND EFFECTIVE DOSE FOR NEUTRON ENERGY SPECTRUM OF 252CF 2001
CONVERSION FACTORS FOR AMBIENT DOSE EQUIVALENTS FOR PHOTONS FROM MEDICAL LINEAR ACCELERATORS 2001
A MONTE CARLO INVESTIGATION OF ABSORBED DOSE DISTRIBUTION IN HEAD PHANTOM IN BORO NEUTRON CAPTURE THERAPY USING AN EPITHERMAL NEUTRON BEAM 2001
APPLICATION OF THE TOMOGRAPHY WITH NEUTRONS IN THE LOCALIZATION OF THE INSCRUSTATIONS IN HEAVY MATERIALS 2001
VOID FRACTION CALCULATIONS IN TWO-PHASE USING NEUTRON RADIOGRAPHY 2001
MONTE CARLO SIMULATION USING MCNP4B FOR AN OPTIMAL SHIELDING OF A 252CF SOURCE 2001
ESPECTROS CLINICOS GERADOS APOS ATRAVESSAREM BARREIRAS DE CONCRETO DE UMA INSTALAÇÃO DE RADIOTERAPIA USANDO O METODO MONTE CARLO 2001
USO THE THERMAL NEUTRON ANALYSIS IN CONJUNCTION WITH NEURAL NETWORKS FOR DETECTION OF EXPLOSIVES 2001
APPLICATION OF NEUTRON RADIOGRAPHY FOR THE DETECTION OF PLASTIC EXPLOSIVES 2001
CÁLCULO DOS FATORES DE CONVERSÃO DE KERMA NO AR PARA EQUVALENTE DE DOSE AMBIENTAL PARA FEIXE DE FÓTONS MONOENERGÉTICOS ENTRE 0,01 MeV e 50 MeV 2001
PERFILES DE DOSIS EM TOMOGRAFIA COMPUTARIZADA SIMULADOS POR MONTE CARLO 2001
A STUDY OF A NEUTRON RADIOGRAPHY SYSTEM USING 252Cf NEUTRON SOURCE 2000
USE OF THERMAL NEUTRON TOMOGRAPHY FOR THE DETECTION OF DRUGS AND EXPLOSIVES 2000
DETECTION OF DRUGS USING THERMAL RADIOGRAPHY 2000
USE OF ARTIFICIAL NEURAL NETWORKS FOR ILLICIT SUBSTANCE IDENTIFICATION 2000
DETECTION OF PLASTIC EXPLOSIVES USING THERMAL NEUTRON TOMOGRAPHY 2000
USE OF THERMAL NEUTRON TOMOGRAPHY FOR NATIONAL SAFETY 2000
ESTUDO DA INFLUÊNCIA DO ESPALHAMENTO DE NÊUTRONS TÉRMICOS SOBRE OS DADOS DE PROJEÇÕES TOMOGRÁFICAS 2000
DETEÇÃO DE EXPLOSIVOS PLÁSTICOS PORO NEUTRONGRAFIA TÉRMICA 2000
CÁLCULO DOS FATORES DE CONVERSÃO DE KERMA NO AR PARA EQUIVALENTE DE DOSE AMBIENTAL EM RADIOTERAPIA 2000
ESTUDO DE UM SISTEMA DE BLINDAGEM PARA UM IRRADIADOR DE CALIFÓRNIO-252 2000
APLICAÇÃO DE REDES NEURAIS PARA A DETEÇÃO DE SUBSTÂNCIAS ILÍCITAS 2000
SHIELDING DESIGN FOR CALIFORNIUM-252 BASED NEUTRON RADIOGRAPHY SYSTEM 2000
ANÁLISE POR ATIVAÇÃO COM NÊUTRONS TÉRMICOS PARA A DETEÇÃO DE SUBSTÂNCIAS ILÍCITAS: UMA SIMULAÇÃO MONTE CARLO. 2000
APLICAÇÃO DA RADIOGRAFIA COM NÊUTRONS TÉRMICOS NA SEGURANÇA PÚBLICA NACIONALl 2000
CÁLCULOS DOS FATORES DE CONVERSÃO H*/Kar, PARA FEIXES REALÍSTICOS EM INSTALAÇÕES EM INSTALAÇÕES DE TRATAMENTO RADIOTERÁPICO 2000
RADIATION QUALITY OF SCATTERED PHOTON AT THE WALLl EXIT OF RADIOTHERAPY ROOMS FOR PHOTONS SPECTRUM CLINICA 2000
DESENVOLVIMENTO DE UM SISTEMA NEUTRONGRÁFICO TRANSPORTÁVEL COM BAIXO FLUXO 1999
DETEÇÃO DE DROGAS POR NEUTRONGRAFIA 1999
UTILIZAÇÃO DE UM SISTEMA ALTERNATIVO DE VARREDURA DE NEUTRONGRAFIA PARA TOMOGRAFIA DE AMOSTRA 1999
NEUTRON RADIOGRAPHY APPLIED AGAINST NARCOTICS TRAFFICKING AND TERRORISM 1999
DESENVOLVIMENTO DE UM SISTEMA NEUTRONGRÁFICO TRANSPORTÁVEL PARA APLICAÇÃO EM ENSAIOS-NÃO DESTRUTIVOS. 1999
Perda de Energia de Fragmentos de Fissão de 252-Cf em Makrofol 1994
Perda de Energia de Prótons em Detectores Sólidos de Traços Nucleares CR-39 e Alumínio 1993
Propriedades de Detecção de Prótons em CR-39 1993
Energia de Ativação do Processo de Annealing de Traços de Partículas Alfa do 241-Am em Detectores Polímeros CR-39 1993
Estudo de Propriedades de Registro de Traços Fósseis de Fragmentos de Fissão em Mica Muscovita 1992
Estudo de Annealing no Registro de Traços de Partículas Alfa do 241-Am em CR-39 1992
Estudo de Propriedades de Registro de Traços Fósseis de Fragmentos de Fissão em Mica Muscovita 1992
Estudos do Annealing de Traços de Prótons de Energia entre 1 e 24 MeV em Detectores Polímeros CR-39 1992
Efeitos de Annealing do Registro de Traços de Partículas Alfa do 241-Am em Detectores CR-39. 1991
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