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Monte Carlo-neutron- och partikeltransport×Strålskyddsdesign×
ÄmnesområdeKärnfysikKärnfysik
FamiljProcess / pipelineProcess / pipeline
Ursprungsår19491898
UpphovspersonNicholas Metropolis, Stanislaw UlamErnest Rutherford, Pierre Curie
Typprobabilistic computational methodengineering design methodology
UrsprungskällaMetropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill. link ↗
AliasMonte Carlo simulation, stochastic transport, particle history methodshield analysis, attenuation design, dose reduction engineering
Närliggande55
SammanfattningMonte 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.Radiation shielding design is an engineering discipline that uses physics-based calculations and materials selection to reduce radiation exposure to acceptable levels, originating from Curie and Rutherford's early radiation studies in the 1890s. By combining attenuation theory, source characterization, and dose modeling, it determines material composition, thickness, and geometry to protect workers, the public, and sensitive equipment.
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ScholarGateJämför metoder: Monte Carlo Neutron & Particle Transport · Radiation Shielding Design. Hämtad 2026-06-20 från https://scholargate.app/sv/compare