手法を比較
選択した手法を並べて確認できます。異なる行はハイライト表示されます。
| 臨界安全性解析× | 中性子輸送計算× | |
|---|---|---|
| 分野 | 原子核物理学 | 原子核物理学 |
| 系統 | Process / pipeline | Process / pipeline |
| 提唱年≠ | 1938 | 1942 |
| 提唱者≠ | Otto Hahn, Fritz Strassmann | Enrico Fermi, Leslie Szilard |
| 種類≠ | safety assessment methodology | computational simulation pipeline |
| 原典≠ | American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40. link ↗ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ |
| 別名 | nuclear safety assessment, chain reaction analysis, fissile material control | neutron diffusion, neutron migration, transport equation solution |
| 関連 | 5 | 5 |
| 概要≠ | 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. | 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. |
| ScholarGateデータセット ↗ |
|
|