ScholarGate
Assistent

Sammenlign metoder

Gennemgå dine valgte metoder side om side; rækker, der afviger, er fremhævet.

Monte Carlo Neutron & Partikeltransport×Strålingsafskærmningsdesign×
FagområdeKernefysikKernefysik
FamilieProcess / pipelineProcess / pipeline
Oprindelsesår19491898
OphavspersonNicholas Metropolis, Stanislaw UlamErnest Rutherford, Pierre Curie
Typeprobabilistic computational methodengineering design methodology
Oprindelig kildeMetropolis, 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 ↗
AliasserMonte Carlo simulation, stochastic transport, particle history methodshield analysis, attenuation design, dose reduction engineering
Relaterede55
ResuméMonte 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.
ScholarGateDatasæt
  1. v1
  2. 2 Kilder
  3. PUBLISHED
  1. v1
  2. 2 Kilder
  3. PUBLISHED

Gå til søgning Hent slides

ScholarGateSammenlign metoder: Monte Carlo Neutron & Particle Transport · Radiation Shielding Design. Hentet 2026-06-19 fra https://scholargate.app/da/compare