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| 원자로 동역학× | Neutron Transport Calculation× | |
|---|---|---|
| 분야 | 핵물리학 | 핵물리학 |
| 계열 | Process / pipeline | Process / pipeline |
| 기원 연도 | 1942 | 1942 |
| 창시자≠ | Enrico Fermi, George Westinghouse | Enrico Fermi, Leslie Szilard |
| 유형≠ | dynamic systems analysis | computational simulation pipeline |
| 원전≠ | Lamarsh, J. R. (1983). Introduction to Nuclear Engineering (2nd ed.). Addison-Wesley. link ↗ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ |
| 별칭 | neutron kinetics, power transient modeling, reactor control analysis | neutron diffusion, neutron migration, transport equation solution |
| 관련 | 5 | 5 |
| 요약≠ | 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. | Neutron transport calculation is a computational method for determining the distribution and behavior of neutrons in a nuclear medium, developed during the Manhattan Project in the 1940s. It solves the Boltzmann transport equation to predict neutron flux, energy spectra, and reaction rates essential for reactor design and shielding analysis. |
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