A. X. Silva

发表

Methodology for digital radiography simulation using the Monte Carlo code MCNPX for industrial applications.

E. M. Souza, S.C.A. Correa, A. X. Silva, 2008, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

CALCULATION OF AVERAGE CONVERSION COEFICIENTS FOR AIR KERMA TO EFFECTIVE DOSE FOR DIAGNOSTIC X-RAY BEAMS

A. X. Silva, A. Kelecom, 2007 .

Neutron dose calculation at the maze entrance of medical linear accelerator rooms.

A. X. Silva, A. Facure, R. C. Falcão, 2007, Radiation protection dosimetry.

A study of neutron spectra from medical linear accelerators.

A. X. Silva, V. R. Crispim, A. Facure, 2005, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Neutron scattering in concrete and wood.

A. X. Silva, V. R. Crispim, A. Facure, 2006, Radiation protection dosimetry.

Multileaf shielding design against neutrons produced by medical linear accelerators.

A. X. Silva, A. Facure, W. Rebello, 2007, Radiation protection dosimetry.

The use of high-density concretes in radiotherapy treatment room design.

A. X. Silva, A. Facure, 2007, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Neutron scattering in concrete and wood: Part II--Oblique incidence.

A. X. Silva, A. Facure, R. C. Falcão, 2007, Radiation Protection Dosimetry.

Thermal annealing of proton tracks with energies of 4 and 6 MeV in CR-39 polymer detectors

A. X. Silva, V. Sciani, P. Rela, 1994 .

CALCULATION OF FLUENCE-TO-AMBIENT DOSE EQUIVALENT CONVERSION COEFFICIENTS FOR NEUTRON ENERGIES BETWEEN 100 keV AND 10 MeV USING MCNPX CODE

A. X. Silva, J. Junior, Selma P. Jesus, 2007 .

Calculation of conversion coefficients for air kerma to ambient dose equivalent using transmitted spectra of megavoltage X-rays through concrete.

A. X. Silva, T. Cordeiro, 2012, Radiation protection dosimetry.

Characterization of a two-component thermoluminescent albedo dosemeter according to ISO 21909

A. X. Silva, M. M. Martins, C. Maurício, 2011 .

Diagnostic assessment to estimate and minimize neutron dose rates received by occupationally exposed individuals at cyclotron facilities.

A. X. Silva, J. C. Suita, A. Facure, 2010, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Studies of isochronal and isothermal annealing of alpha particle tracks in CR-39 polymer detectors

A. X. Silva, J. D. P. Filho, R. Santos, 1996 .

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

A. X. Silva, D. Braz, J. Lopes, 2018, Radiation protection dosimetry.

Comparison of simulated and experimental values of self-absorption correction factors for a fast and credible adjust in efficiency curve of gamma spectroscopy.

A. X. Silva, J. L. Thalhofer, J. Lopes, 2018, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Detection of drugs and explosives using neutron computerized tomography and artificial intelligence techniques.

A. X. Silva, V. R. Crispim, F J O Ferreira, 2010, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Monte Carlo simulation of response function for a NaI(Tl) detector for gamma rays from 241Am/Be source.

A. X. Silva, V. R. Crispim, J. C. Vitorelli, 2005, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Use of gamma radiation and artificial neural network techniques to monitor characteristics of polyduct transport of petroleum by-products.

A. X. Silva, C. M. Salgado, R. Dam, 2022, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Computed radiography simulation using the Monte Carlo code MCNPX.

E. M. Souza, A. X. Silva, A X Silva, 2010, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.