Comparar métodos

	Transporte de Nêutrons e Partículas por Monte Carlo	Avaliação da Dose de Radiação
Área	Física nuclear	Física nuclear
Família	Process / pipeline	Process / pipeline
Ano de origem	1949	1928
Autor original	Nicholas Metropolis, Stanislaw Ulam	International Commission on Radiological Protection (ICRP)
Tipo	probabilistic computational method	computational health assessment pipeline
Fonte seminal	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.	International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4).
Outros nomes	Monte Carlo simulation, stochastic transport, particle history method	dose calculation, exposure assessment, radiation hazard evaluation
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 dose assessment is a systematic evaluation of human exposure to ionizing radiation from external or internal sources, formalized by the International Commission on Radiological Protection (ICRP) in the late 20th century. It combines radiation transport calculations with biological effect models to quantify absorbed dose, equivalent dose, and effective dose for worker safety and public health protection.