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Nøytrontransportberegning×Strålingsskjermingsdesign×
FagfeltKjernefysikkKjernefysikk
FamilieProcess / pipelineProcess / pipeline
Opprinnelsesår19421898
OpphavspersonEnrico Fermi, Leslie SzilardErnest Rutherford, Pierre Curie
Typecomputational simulation pipelineengineering design methodology
Opprinnelig kildeDuderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons. link ↗Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill. link ↗
Aliasneutron diffusion, neutron migration, transport equation solutionshield analysis, attenuation design, dose reduction engineering
Relaterte55
SammendragNeutron transport calculation is a computational method for determining the distribution and behavior of neutrons in a nuclear medium, developed during the Manhattan Project in the 1940s. It solves the Boltzmann transport equation to predict neutron flux, energy spectra, and reaction rates essential for reactor design and shielding analysis.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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ScholarGateSammenlign metoder: Neutron Transport Calculation · Radiation Shielding Design. Hentet 2026-06-19 fra https://scholargate.app/no/compare