مقایسهٔ روش‌ها

	حمل و نقل نوترون و ذرات به روش مونت کارلو	تحلیل ایمنی بحرانایی
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1949	1938
پدیدآور	Nicholas Metropolis, Stanislaw Ulam	Otto Hahn, Fritz Strassmann
نوع	probabilistic computational method	safety assessment methodology
منبع بنیادین	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.	American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40.
نام‌های دیگر	Monte Carlo simulation, stochastic transport, particle history method	nuclear safety assessment, chain reaction analysis, fissile material control
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.	Criticality safety analysis is a systematic evaluation of fissile material systems to ensure nuclear chain reactions remain controlled, originating from Hahn and Strassmann's 1938 discovery of nuclear fission. It determines safe limits on fissile mass, concentration, geometry, and spacing using neutron transport calculations and experimental validation to prevent uncontrolled nuclear excursions in storage, processing, and transportation.