Porovnať metódy

	Kinetika reaktorov	Neutrónová a časticová doprava metódou Monte Carlo
Odbor	Jadrová fyzika	Jadrová fyzika
Rodina	Process / pipeline	Process / pipeline
Rok vzniku	1942	1949
Tvorca	Enrico Fermi, George Westinghouse	Nicholas Metropolis, Stanislaw Ulam
Typ	dynamic systems analysis	probabilistic computational method
Pôvodný zdroj	Lamarsh, J. R. (1983). Introduction to Nuclear Engineering (2nd ed.). Addison-Wesley.	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.
Ďalšie názvy	neutron kinetics, power transient modeling, reactor control analysis	Monte Carlo simulation, stochastic transport, particle history method
Príbuzné	5	5
Zhrnutie	Reactor kinetics is the study of neutron population dynamics in a reactor core, originating from Fermi's first controlled chain reaction in 1942. It models power changes in response to control rod movements, temperature feedback, and accidental transients using coupled differential equations accounting for prompt and delayed neutrons, to ensure safe operation, predict transient behavior, and design control systems.	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.