Порівняння методів

	Оцінка радіаційної дози	Нейтронний та частинковий транспорт Монте-Карло
Галузь	Ядерна фізика	Ядерна фізика
Родина	Process / pipeline	Process / pipeline
Рік появи	1928	1949
Автор методу	International Commission on Radiological Protection (ICRP)	Nicholas Metropolis, Stanislaw Ulam
Тип	computational health assessment pipeline	probabilistic computational method
Основоположне джерело	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.
Інші назви	dose calculation, exposure assessment, radiation hazard evaluation	Monte Carlo simulation, stochastic transport, particle history method
Пов'язані	5	5
Підсумок	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.