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モンテカルロ中性子・粒子輸送×放射線遮蔽設計×
分野原子核物理学原子核物理学
系統Process / pipelineProcess / pipeline
提唱年19491898
提唱者Nicholas Metropolis, Stanislaw UlamErnest Rutherford, Pierre Curie
種類probabilistic computational methodengineering design methodology
原典Metropolis, 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 ↗
別名Monte Carlo simulation, stochastic transport, particle history methodshield analysis, attenuation design, dose reduction engineering
関連55
概要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.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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ScholarGate手法を比較: Monte Carlo Neutron & Particle Transport · Radiation Shielding Design. 2026-06-19に以下より取得 https://scholargate.app/ja/compare