Compară metode

	Cinetica Reactorului	Transport de Neutroni și Particule Monte Carlo
Domeniu	Fizică nucleară	Fizică nucleară
Familie	Process / pipeline	Process / pipeline
Anul apariției	1942	1949
Autorul original	Enrico Fermi, George Westinghouse	Nicholas Metropolis, Stanislaw Ulam
Tip	dynamic systems analysis	probabilistic computational method
Sursa seminală	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.
Denumiri alternative	neutron kinetics, power transient modeling, reactor control analysis	Monte Carlo simulation, stochastic transport, particle history method
Înrudite	5	5
Rezumat	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.