Сравнение на методи
Прегледайте избраните методи един до друг; редовете с разлики са откроени.
| Анализ на цикъла на ядреното гориво× | Оценка на радиационната доза× | |
|---|---|---|
| Област | Ядрена физика | Ядрена физика |
| Семейство | Process / pipeline | Process / pipeline |
| Година на възникване≠ | 1942 | 1928 |
| Създател≠ | Enrico Fermi, Alvin Weinberg | International Commission on Radiological Protection (ICRP) |
| Тип≠ | system-level material and energy accounting | computational health assessment pipeline |
| Основополагащ източник≠ | International Atomic Energy Agency (2021). Nuclear Fuel Cycle Information System (NFCIS). IAEA-NDS-3/Rev.2. link ↗ | International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4). link ↗ |
| Други названия | fuel cycle modeling, material accounting, energy lifecycle assessment | dose calculation, exposure assessment, radiation hazard evaluation |
| Свързани | 5 | 5 |
| Резюме≠ | Nuclear fuel cycle analysis is a comprehensive assessment of uranium and plutonium flows from extraction through enrichment, power generation, and waste management, originating from Fermi's controlled nuclear reaction. It quantifies resource requirements, energy balances, greenhouse gas emissions, and waste streams to evaluate nuclear energy sustainability, proliferation risk, and economic viability. | 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. |
| ScholarGateНабор от данни ↗ |
|
|