方法对比
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| 蒙特卡洛中子与粒子输运× | 中子输运计算× | |
|---|---|---|
| 领域 | 核物理学 | 核物理学 |
| 方法族 | Process / pipeline | Process / pipeline |
| 起源年份≠ | 1949 | 1942 |
| 提出者≠ | Nicholas Metropolis, Stanislaw Ulam | Enrico Fermi, Leslie Szilard |
| 类型≠ | probabilistic computational method | computational simulation pipeline |
| 开创性文献≠ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ | Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗ |
| 别名 | Monte Carlo simulation, stochastic transport, particle history method | neutron diffusion, neutron migration, transport equation solution |
| 相关 | 5 | 5 |
| 摘要≠ | 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. | 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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