مقایسهٔ روشها
روشهای انتخابی خود را کنار هم مرور کنید؛ ردیفهای متفاوت برجسته شدهاند.
| سینتیک راکتور× | ارزیابی دوز پرتو× | |
|---|---|---|
| حوزه | فیزیک هستهای | فیزیک هستهای |
| خانواده | Process / pipeline | Process / pipeline |
| سال پیدایش≠ | 1942 | 1928 |
| پدیدآور≠ | Enrico Fermi, George Westinghouse | International Commission on Radiological Protection (ICRP) |
| نوع≠ | dynamic systems analysis | computational health assessment pipeline |
| منبع بنیادین≠ | Lamarsh, J. R. (1983). Introduction to Nuclear Engineering (2nd ed.). Addison-Wesley. link ↗ | International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4). link ↗ |
| نامهای دیگر | neutron kinetics, power transient modeling, reactor control analysis | dose calculation, exposure assessment, radiation hazard evaluation |
| مرتبط | 5 | 5 |
| خلاصه≠ | Reactor kinetics is the study of neutron population dynamics in a reactor core, originating from Fermi's first controlled chain reaction in 1942. It models power changes in response to control rod movements, temperature feedback, and accidental transients using coupled differential equations accounting for prompt and delayed neutrons, to ensure safe operation, predict transient behavior, and design control systems. | 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. |
| ScholarGateمجموعهداده ↗ |
|
|