مقایسهٔ روش‌ها

	حمل و نقل نوترون و ذرات به روش مونت کارلو	محاسبه انتقال نوترون
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1949	1942
پدیدآور	Nicholas Metropolis, Stanislaw Ulam	Enrico Fermi, Leslie Szilard
نوع	probabilistic computational method	computational simulation pipeline
منبع بنیادین	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.	Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons.
نام‌های دیگر	Monte Carlo simulation, stochastic transport, particle history method	neutron diffusion, neutron migration, transport equation solution
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.	Neutron transport calculation is a computational method for determining the distribution and behavior of neutrons in a nuclear medium, developed during the Manhattan Project in the 1940s. It solves the Boltzmann transport equation to predict neutron flux, energy spectra, and reaction rates essential for reactor design and shielding analysis.