Comparar métodos
Revisa los métodos seleccionados uno junto a otro; las filas que difieren aparecen resaltadas.
| Cinética de Reactores× | Transporte de neutrones y partículas por Monte Carlo× | |
|---|---|---|
| Campo | Física nuclear | Física nuclear |
| Familia | Process / pipeline | Process / pipeline |
| Año de origen≠ | 1942 | 1949 |
| Autor original≠ | Enrico Fermi, George Westinghouse | Nicholas Metropolis, Stanislaw Ulam |
| Tipo≠ | dynamic systems analysis | probabilistic computational method |
| Fuente seminal≠ | Lamarsh, J. R. (1983). Introduction to Nuclear Engineering (2nd ed.). Addison-Wesley. link ↗ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ |
| Alias | neutron kinetics, power transient modeling, reactor control analysis | Monte Carlo simulation, stochastic transport, particle history method |
| Relacionados | 5 | 5 |
| Resumen≠ | 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. |
| ScholarGateConjunto de datos ↗ |
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