Methoden vergleichen

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