مقایسهٔ روش‌ها

	طراحی حفاظ تابشی	حمل و نقل نوترون و ذرات به روش مونت کارلو
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1898	1949
پدیدآور	Ernest Rutherford, Pierre Curie	Nicholas Metropolis, Stanislaw Ulam
نوع	engineering design methodology	probabilistic computational method
منبع بنیادین	Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill.	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.
نام‌های دیگر	shield analysis, attenuation design, dose reduction engineering	Monte Carlo simulation, stochastic transport, particle history method
مرتبط	5	5
خلاصه	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.	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.