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| Calcul du transport de neutrons× | Analyse de sûreté-criticité× | |
|---|---|---|
| Domaine | Physique nucléaire | Physique nucléaire |
| Famille | Process / pipeline | Process / pipeline |
| Année d'origine≠ | 1942 | 1938 |
| Auteur d'origine≠ | Enrico Fermi, Leslie Szilard | Otto Hahn, Fritz Strassmann |
| Type≠ | computational simulation pipeline | safety assessment methodology |
| Source fondatrice≠ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ | American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40. link ↗ |
| Alias | neutron diffusion, neutron migration, transport equation solution | nuclear safety assessment, chain reaction analysis, fissile material control |
| Apparentées | 5 | 5 |
| Résumé≠ | 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. | 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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