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| Transport de neutrons et de particules par Monte Carlo× | Calcul du transport de neutrons× | |
|---|---|---|
| Domaine | Physique nucléaire | Physique nucléaire |
| Famille | Process / pipeline | Process / pipeline |
| Année d'origine≠ | 1949 | 1942 |
| Auteur d'origine≠ | Nicholas Metropolis, Stanislaw Ulam | Enrico Fermi, Leslie Szilard |
| Type≠ | probabilistic computational method | computational simulation pipeline |
| Source fondatrice≠ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ |
| Alias | Monte Carlo simulation, stochastic transport, particle history method | neutron diffusion, neutron migration, transport equation solution |
| Apparentées | 5 | 5 |
| Résumé≠ | 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. | 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. |
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