Сравнение методов
Просматривайте выбранные методы рядом; строки с различиями подсвечены.
| Оценка дозы облучения× | Расчёт нейтронных переносов× | |
|---|---|---|
| Область | Ядерная физика | Ядерная физика |
| Семейство | Process / pipeline | Process / pipeline |
| Год появления≠ | 1928 | 1942 |
| Автор метода≠ | International Commission on Radiological Protection (ICRP) | Enrico Fermi, Leslie Szilard |
| Тип≠ | computational health assessment pipeline | computational simulation pipeline |
| Основополагающий источник≠ | International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4). link ↗ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ |
| Другие названия | dose calculation, exposure assessment, radiation hazard evaluation | neutron diffusion, neutron migration, transport equation solution |
| Связанные | 5 | 5 |
| Сводка≠ | Radiation dose assessment is a systematic evaluation of human exposure to ionizing radiation from external or internal sources, formalized by the International Commission on Radiological Protection (ICRP) in the late 20th century. It combines radiation transport calculations with biological effect models to quantify absorbed dose, equivalent dose, and effective dose for worker safety and public health protection. | 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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