Comparar métodos
Revisa los métodos seleccionados uno junto a otro; las filas que difieren aparecen resaltadas.
| Transporte de neutrones y partículas por Monte Carlo× | Análisis de Seguridad de Criticidad× | |
|---|---|---|
| Campo | Física nuclear | Física nuclear |
| Familia | Process / pipeline | Process / pipeline |
| Año de origen≠ | 1949 | 1938 |
| Autor original≠ | Nicholas Metropolis, Stanislaw Ulam | Otto Hahn, Fritz Strassmann |
| Tipo≠ | probabilistic computational method | safety assessment methodology |
| Fuente seminal≠ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ | American National Standards Institute (2019). Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors. ANSI/ANS-8.1-19.40. link ↗ |
| Alias | Monte Carlo simulation, stochastic transport, particle history method | nuclear safety assessment, chain reaction analysis, fissile material control |
| Relacionados | 5 | 5 |
| Resumen≠ | Monte Carlo neutron and particle transport is a stochastic simulation method that tracks individual particle histories through matter, developed by Metropolis and Ulam in 1949 during the Manhattan Project. By sampling random numbers to determine collision locations, energy transfers, and scattering angles, it produces unbiased estimates of reaction rates, flux distributions, and detector responses without discretizing angle or energy variables. | 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. |
| ScholarGateConjunto de datos ↗ |
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