Methoden vergleichen

	Kritikalitätssicherheitsanalyse	Monte-Carlo-Neutronen- und Teilchentransport
Fachgebiet	Kernphysik	Kernphysik
Familie	Process / pipeline	Process / pipeline
Entstehungsjahr	1938	1949
Urheber	Otto Hahn, Fritz Strassmann	Nicholas Metropolis, Stanislaw Ulam
Typ	safety assessment methodology	probabilistic computational method
Wegweisende Quelle	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.
Aliasnamen	nuclear safety assessment, chain reaction analysis, fissile material control	Monte Carlo simulation, stochastic transport, particle history method
Verwandt	5	5
Zusammenfassung	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.