Порівняння методів
Переглядайте обрані методи поруч; рядки з відмінностями підсвічено.
| Нейтронний та частинковий транспорт Монте-Карло× | Проєктування радіаційного захисту× | |
|---|---|---|
| Галузь | Ядерна фізика | Ядерна фізика |
| Родина | Process / pipeline | Process / pipeline |
| Рік появи≠ | 1949 | 1898 |
| Автор методу≠ | Nicholas Metropolis, Stanislaw Ulam | Ernest Rutherford, Pierre Curie |
| Тип≠ | probabilistic computational method | engineering design methodology |
| Основоположне джерело≠ | 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 ↗ |
| Інші назви | Monte Carlo simulation, stochastic transport, particle history method | shield analysis, attenuation design, dose reduction engineering |
| Пов'язані | 5 | 5 |
| Підсумок≠ | 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. |
| ScholarGateНабір даних ↗ |
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