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