Comparer des méthodes

	Conception de la protection radiologique	Calcul du transport de neutrons
Domaine	Physique nucléaire	Physique nucléaire
Famille	Process / pipeline	Process / pipeline
Année d'origine	1898	1942
Auteur d'origine	Ernest Rutherford, Pierre Curie	Enrico Fermi, Leslie Szilard
Type	engineering design methodology	computational simulation pipeline
Source fondatrice	Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill.	Duderstadt, J. J., & Hamilton, L. J. (1976). Nuclear Reactor Analysis. John Wiley & Sons.
Alias	shield analysis, attenuation design, dose reduction engineering	neutron diffusion, neutron migration, transport equation solution
Apparentées	5	5
Résumé	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.	Neutron 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.