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| Neutron transport calculation× | Säteilyannosarviointi× | |
|---|---|---|
| Tieteenala | Ydinfysiikka | Ydinfysiikka |
| Menetelmäperhe | Process / pipeline | Process / pipeline |
| Syntyvuosi≠ | 1942 | 1928 |
| Kehittäjä≠ | Enrico Fermi, Leslie Szilard | International Commission on Radiological Protection (ICRP) |
| Tyyppi≠ | computational simulation pipeline | computational health assessment pipeline |
| Alkuperäislähde≠ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ | International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4). link ↗ |
| Rinnakkaisnimet | neutron diffusion, neutron migration, transport equation solution | dose calculation, exposure assessment, radiation hazard evaluation |
| Liittyvät | 5 | 5 |
| Tiivistelmä≠ | 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. | 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. |
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