方法对比
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| 反应堆动力学× | 临界安全分析× | |
|---|---|---|
| 领域 | 核物理学 | 核物理学 |
| 方法族 | Process / pipeline | Process / pipeline |
| 起源年份≠ | 1942 | 1938 |
| 提出者≠ | Enrico Fermi, George Westinghouse | Otto Hahn, Fritz Strassmann |
| 类型≠ | dynamic systems analysis | safety assessment methodology |
| 开创性文献≠ | Lamarsh, J. R. (1983). Introduction to Nuclear Engineering (2nd ed.). Addison-Wesley. link ↗ | American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40. link ↗ |
| 别名 | neutron kinetics, power transient modeling, reactor control analysis | nuclear safety assessment, chain reaction analysis, fissile material control |
| 相关 | 5 | 5 |
| 摘要≠ | 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. | Criticality safety analysis is a systematic evaluation of fissile material systems to ensure nuclear chain reactions remain controlled, originating from Hahn and Strassmann's 1938 discovery of nuclear fission. It determines safe limits on fissile mass, concentration, geometry, and spacing using neutron transport calculations and experimental validation to prevent uncontrolled nuclear excursions in storage, processing, and transportation. |
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