Comparer des méthodes
Examinez les méthodes sélectionnées côte à côte ; les lignes qui diffèrent sont mises en évidence.
| Transport de neutrons et de particules par Monte Carlo× | Conception de la protection radiologique× | |
|---|---|---|
| Domaine | Physique nucléaire | Physique nucléaire |
| Famille | Process / pipeline | Process / pipeline |
| Année d'origine≠ | 1949 | 1898 |
| Auteur d'origine≠ | Nicholas Metropolis, Stanislaw Ulam | Ernest Rutherford, Pierre Curie |
| Type≠ | probabilistic computational method | engineering design methodology |
| Source fondatrice≠ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ | Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill. link ↗ |
| Alias | Monte Carlo simulation, stochastic transport, particle history method | shield analysis, attenuation design, dose reduction engineering |
| 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. | Radiation shielding design is an engineering discipline that uses physics-based calculations and materials selection to reduce radiation exposure to acceptable levels, originating from Curie and Rutherford's early radiation studies in the 1890s. By combining attenuation theory, source characterization, and dose modeling, it determines material composition, thickness, and geometry to protect workers, the public, and sensitive equipment. |
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