مقایسهٔ روش‌ها

	تحلیل ایمنی بحرانایی	حمل و نقل نوترون و ذرات به روش مونت کارلو
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1938	1949
پدیدآور	Otto Hahn, Fritz Strassmann	Nicholas Metropolis, Stanislaw Ulam
نوع	safety assessment methodology	probabilistic computational method
منبع بنیادین	American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40.	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.
نام‌های دیگر	nuclear safety assessment, chain reaction analysis, fissile material control	Monte Carlo simulation, stochastic transport, particle history method
مرتبط	5	5
خلاصه	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.	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.