Compara mètodes

	Cinètica de reactors	Transport de neutrons i partícules per Monte Carlo
Camp	Física nuclear	Física nuclear
Família	Process / pipeline	Process / pipeline
Any d'origen	1942	1949
Autor original	Enrico Fermi, George Westinghouse	Nicholas Metropolis, Stanislaw Ulam
Tipus	dynamic systems analysis	probabilistic computational method
Font seminal	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.
Àlies	neutron kinetics, power transient modeling, reactor control analysis	Monte Carlo simulation, stochastic transport, particle history method
Relacionats	5	5
Resum	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.