השוואת שיטות

	חישוב הולכת נייטרונים	תחבורת ניוטרונים וחלקיקים בשיטת מונטה קרלו
תחום	פיזיקה גרעינית	פיזיקה גרעינית
משפחה	Process / pipeline	Process / pipeline
שנת המקור	1942	1949
הוגה השיטה	Enrico Fermi, Leslie Szilard	Nicholas Metropolis, Stanislaw Ulam
סוג	computational simulation pipeline	probabilistic computational method
מקור מכונן	Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons.	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.
כינויים	neutron diffusion, neutron migration, transport equation solution	Monte Carlo simulation, stochastic transport, particle history method
קשורות	5	5
תקציר	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.	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.