Comparer des méthodes

	Analyse de sûreté-criticité	Transport de neutrons et de particules par Monte Carlo
Domaine	Physique nucléaire	Physique nucléaire
Famille	Process / pipeline	Process / pipeline
Année d'origine	1938	1949
Auteur d'origine	Otto Hahn, Fritz Strassmann	Nicholas Metropolis, Stanislaw Ulam
Type	safety assessment methodology	probabilistic computational method
Source fondatrice	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.
Alias	nuclear safety assessment, chain reaction analysis, fissile material control	Monte Carlo simulation, stochastic transport, particle history method
Apparentées	5	5
Résumé	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.