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| Ocena dawki promieniowania× | Monte Carlo w transporcie neutronów i cząstek× | |
|---|---|---|
| Dziedzina | Fizyka jądrowa | Fizyka jądrowa |
| Rodzina | Process / pipeline | Process / pipeline |
| Rok powstania≠ | 1928 | 1949 |
| Twórca≠ | International Commission on Radiological Protection (ICRP) | Nicholas Metropolis, Stanislaw Ulam |
| Typ≠ | computational health assessment pipeline | probabilistic computational method |
| Źródło pierwotne≠ | 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 ↗ |
| Inne nazwy | dose calculation, exposure assessment, radiation hazard evaluation | Monte Carlo simulation, stochastic transport, particle history method |
| Pokrewne | 5 | 5 |
| Podsumowanie≠ | 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. |
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