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| 临界安全分析× | 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≠ | 1938 | 1942 |
| 提出者≠ | Otto Hahn, Fritz Strassmann | Enrico Fermi, George Westinghouse |
| 类型≠ | safety assessment methodology | dynamic systems analysis |
| 开创性文献≠ | American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40. link ↗ | Lamarsh, J. R. (1983). Introduction to Nuclear Engineering (2nd ed.). Addison-Wesley. link ↗ |
| 别名 | nuclear safety assessment, chain reaction analysis, fissile material control | neutron kinetics, power transient modeling, reactor control analysis |
| 相关 | 5 | 5 |
| 摘要≠ | 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. | 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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