Сравнение методов
Просматривайте выбранные методы рядом; строки с различиями подсвечены.
| Monte Carlo Neutron & Particle Transport× | Проектирование радиационной защиты× | |
|---|---|---|
| Область | Ядерная физика | Ядерная физика |
| Семейство | Process / pipeline | Process / pipeline |
| Год появления≠ | 1949 | 1898 |
| Автор метода≠ | Nicholas Metropolis, Stanislaw Ulam | Ernest Rutherford, Pierre Curie |
| Тип≠ | probabilistic computational method | engineering design methodology |
| Основополагающий источник≠ | 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 ↗ |
| Другие названия | Monte Carlo simulation, stochastic transport, particle history method | shield analysis, attenuation design, dose reduction engineering |
| Связанные | 5 | 5 |
| Сводка≠ | 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. |
| ScholarGateНабор данных ↗ |
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