مقایسهٔ روش‌ها

	حمل و نقل نوترون و ذرات به روش مونت کارلو	طراحی حفاظ تابشی
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1949	1898
پدیدآور	Nicholas Metropolis, Stanislaw Ulam	Ernest Rutherford, Pierre Curie
نوع	probabilistic computational method	engineering design methodology
منبع بنیادین	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.
نام‌های دیگر	Monte Carlo simulation, stochastic transport, particle history method	shield analysis, attenuation design, dose reduction engineering
مرتبط	5	5
خلاصه	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.