Porovnat metody
Prohlédněte si vybrané metody vedle sebe; řádky, které se liší, jsou zvýrazněny.
| Výpočet transportu neutronů× | Transport neutronů a částic metodou Monte Carlo× | |
|---|---|---|
| Obor | Jaderná fyzika | Jaderná fyzika |
| Rodina | Process / pipeline | Process / pipeline |
| Rok vzniku≠ | 1942 | 1949 |
| Tvůrce≠ | Enrico Fermi, Leslie Szilard | Nicholas Metropolis, Stanislaw Ulam |
| Typ≠ | computational simulation pipeline | probabilistic computational method |
| Původní zdroj≠ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ |
| Další názvy | neutron diffusion, neutron migration, transport equation solution | Monte Carlo simulation, stochastic transport, particle history method |
| Příbuzné | 5 | 5 |
| Shrnutí≠ | Neutron transport calculation is a computational method for determining the distribution and behavior of neutrons in a nuclear medium, developed during the Manhattan Project in the 1940s. It solves the Boltzmann transport equation to predict neutron flux, energy spectra, and reaction rates essential for reactor design and shielding analysis. | 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. |
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