Jämför metoder
Granska de valda metoderna sida vid sida; rader som skiljer sig är markerade.
| Monte Carlo-neutron- och partikeltransport× | Bedömning av stråldos× | |
|---|---|---|
| Ämnesområde | Kärnfysik | Kärnfysik |
| Familj | Process / pipeline | Process / pipeline |
| Ursprungsår≠ | 1949 | 1928 |
| Upphovsperson≠ | Nicholas Metropolis, Stanislaw Ulam | International Commission on Radiological Protection (ICRP) |
| Typ≠ | probabilistic computational method | computational health assessment pipeline |
| Ursprungskälla≠ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ | International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4). link ↗ |
| Alias | Monte Carlo simulation, stochastic transport, particle history method | dose calculation, exposure assessment, radiation hazard evaluation |
| Närliggande | 5 | 5 |
| Sammanfattning≠ | 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 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. |
| ScholarGateDatamängd ↗ |
|
|