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Monte Carlo neutronite ja osakeste transport×Neutronite transpordi arvutus×
ValdkondTuumafüüsikaTuumafüüsika
PerekondProcess / pipelineProcess / pipeline
Tekkeaasta19491942
LoojaNicholas Metropolis, Stanislaw UlamEnrico Fermi, Leslie Szilard
Tüüpprobabilistic computational methodcomputational simulation pipeline
AlgallikasMetropolis, 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 ↗
RööpnimetusedMonte Carlo simulation, stochastic transport, particle history methodneutron diffusion, neutron migration, transport equation solution
Seotud55
KokkuvõteMonte 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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ScholarGateVõrdle meetodeid: Monte Carlo Neutron & Particle Transport · Neutron Transport Calculation. Loetud 2026-06-20 aadressilt https://scholargate.app/et/compare