Comparar métodos

	Transporte de Nêutrons e Partículas por Monte Carlo	Design de Blindagem contra Radiação
Área	Física nuclear	Física nuclear
Família	Process / pipeline	Process / pipeline
Ano de origem	1949	1898
Autor original	Nicholas Metropolis, Stanislaw Ulam	Ernest Rutherford, Pierre Curie
Tipo	probabilistic computational method	engineering design methodology
Fonte seminal	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.	Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill.
Outros nomes	Monte Carlo simulation, stochastic transport, particle history method	shield analysis, attenuation design, dose reduction engineering
Relacionados	5	5
Resumo	Monte Carlo neutron and particle transport is a stochastic simulation method that tracks individual particle histories through matter, developed by Metropolis and Ulam in 1949 during the Manhattan Project. By sampling random numbers to determine collision locations, energy transfers, and scattering angles, it produces unbiased estimates of reaction rates, flux distributions, and detector responses without discretizing angle or energy variables.	Radiation shielding design is an engineering discipline that uses physics-based calculations and materials selection to reduce radiation exposure to acceptable levels, originating from Curie and Rutherford's early radiation studies in the 1890s. By combining attenuation theory, source characterization, and dose modeling, it determines material composition, thickness, and geometry to protect workers, the public, and sensitive equipment.