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| 核燃料循环分析× | 反应堆动力学× | |
|---|---|---|
| 领域 | 核物理学 | 核物理学 |
| 方法族 | Process / pipeline | Process / pipeline |
| 起源年份 | 1942 | 1942 |
| 提出者≠ | Enrico Fermi, Alvin Weinberg | Enrico Fermi, George Westinghouse |
| 类型≠ | system-level material and energy accounting | dynamic systems analysis |
| 开创性文献≠ | International Atomic Energy Agency (2021). Nuclear Fuel Cycle Information System (NFCIS). IAEA-NDS-3/Rev.2. link ↗ | Lamarsh, J. R. (1983). Introduction to Nuclear Engineering (2nd ed.). Addison-Wesley. link ↗ |
| 别名 | fuel cycle modeling, material accounting, energy lifecycle assessment | neutron kinetics, power transient modeling, reactor control analysis |
| 相关 | 5 | 5 |
| 摘要≠ | 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. | 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. |
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