Сравнение методов
Просматривайте выбранные методы рядом; строки с различиями подсвечены.
| Оценка дозы облучения× | Monte Carlo Neutron & Particle Transport× | |
|---|---|---|
| Область | Ядерная физика | Ядерная физика |
| Семейство | Process / pipeline | Process / pipeline |
| Год появления≠ | 1928 | 1949 |
| Автор метода≠ | International Commission on Radiological Protection (ICRP) | Nicholas Metropolis, Stanislaw Ulam |
| Тип≠ | computational health assessment pipeline | probabilistic computational method |
| Основополагающий источник≠ | International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4). link ↗ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ |
| Другие названия | dose calculation, exposure assessment, radiation hazard evaluation | Monte Carlo simulation, stochastic transport, particle history method |
| 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. | 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. |
| ScholarGateНабор данных ↗ |
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