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	Projektowanie osłon radiacyjnych	Monte Carlo w transporcie neutronów i cząstek
Dziedzina	Fizyka jądrowa	Fizyka jądrowa
Rodzina	Process / pipeline	Process / pipeline
Rok powstania	1898	1949
Twórca	Ernest Rutherford, Pierre Curie	Nicholas Metropolis, Stanislaw Ulam
Typ	engineering design methodology	probabilistic computational method
Źródło pierwotne	Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill.	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.
Inne nazwy	shield analysis, attenuation design, dose reduction engineering	Monte Carlo simulation, stochastic transport, particle history method
Pokrewne	5	5
Podsumowanie	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.	Monte 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.