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Monte Carlo Neutron & Particle Transport×Проектирование радиационной защиты×
ОбластьЯдерная физикаЯдерная физика
СемействоProcess / pipelineProcess / pipeline
Год появления19491898
Автор методаNicholas Metropolis, Stanislaw UlamErnest Rutherford, Pierre Curie
Типprobabilistic computational methodengineering design methodology
Основополагающий источникMetropolis, 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 ↗
Другие названияMonte Carlo simulation, stochastic transport, particle history methodshield analysis, attenuation design, dose reduction engineering
Связанные55
СводкаMonte 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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ScholarGateСравнение методов: Monte Carlo Neutron & Particle Transport · Radiation Shielding Design. Получено 2026-06-19 из https://scholargate.app/ru/compare