مقایسهٔ روش‌ها

	طراحی حفاظ تابشی	محاسبه انتقال نوترون
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1898	1942
پدیدآور	Ernest Rutherford, Pierre Curie	Enrico Fermi, Leslie Szilard
نوع	engineering design methodology	computational simulation pipeline
منبع بنیادین	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.
نام‌های دیگر	shield analysis, attenuation design, dose reduction engineering	neutron diffusion, neutron migration, transport equation solution
مرتبط	5	5
خلاصه	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.