Compară metode

	Evaluarea Dozei de Radiații	Transport de Neutroni și Particule Monte Carlo
Domeniu	Fizică nucleară	Fizică nucleară
Familie	Process / pipeline	Process / pipeline
Anul apariției	1928	1949
Autorul original	International Commission on Radiological Protection (ICRP)	Nicholas Metropolis, Stanislaw Ulam
Tip	computational health assessment pipeline	probabilistic computational method
Sursa seminală	International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4).	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.
Denumiri alternative	dose calculation, exposure assessment, radiation hazard evaluation	Monte Carlo simulation, stochastic transport, particle history method
Înrudite	5	5
Rezumat	Radiation dose assessment is a systematic evaluation of human exposure to ionizing radiation from external or internal sources, formalized by the International Commission on Radiological Protection (ICRP) in the late 20th century. It combines radiation transport calculations with biological effect models to quantify absorbed dose, equivalent dose, and effective dose for worker safety and public health protection.	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.