So sánh phương pháp

	Động lực học Lò phản ứng	Vận chuyển Neutron & Hạt Monte Carlo
Lĩnh vực	Vật lý hạt nhân	Vật lý hạt nhân
Họ	Process / pipeline	Process / pipeline
Năm ra đời	1942	1949
Người khởi xướng	Enrico Fermi, George Westinghouse	Nicholas Metropolis, Stanislaw Ulam
Loại	dynamic systems analysis	probabilistic computational method
Công trình gốc	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.
Tên gọi khác	neutron kinetics, power transient modeling, reactor control analysis	Monte Carlo simulation, stochastic transport, particle history method
Liên quan	5	5
Tóm tắt	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.