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Transport de neutrons et de particules par Monte Carlo×Conception de la protection radiologique×
DomainePhysique nucléairePhysique nucléaire
FamilleProcess / pipelineProcess / pipeline
Année d'origine19491898
Auteur d'origineNicholas Metropolis, Stanislaw UlamErnest Rutherford, Pierre Curie
Typeprobabilistic computational methodengineering design methodology
Source fondatriceMetropolis, 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
Apparentées55
RésuméMonte 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.
ScholarGateJeu de données
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ScholarGateComparer des méthodes: Monte Carlo Neutron & Particle Transport · Radiation Shielding Design. Consulté le 2026-06-19 sur https://scholargate.app/fr/compare