Сравнение методов
Просматривайте выбранные методы рядом; строки с различиями подсвечены.
| Проектирование радиационной защиты× | Расчёт нейтронных переносов× | |
|---|---|---|
| Область | Ядерная физика | Ядерная физика |
| Семейство | Process / pipeline | Process / pipeline |
| Год появления≠ | 1898 | 1942 |
| Автор метода≠ | Ernest Rutherford, Pierre Curie | Enrico Fermi, Leslie Szilard |
| Тип≠ | engineering design methodology | computational simulation pipeline |
| Основополагающий источник≠ | Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill. link ↗ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ |
| Другие названия | shield analysis, attenuation design, dose reduction engineering | neutron diffusion, neutron migration, transport equation solution |
| Связанные | 5 | 5 |
| Сводка≠ | 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. | 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. |
| ScholarGateНабор данных ↗ |
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