مقایسهٔ روش‌ها

	حمل و نقل نوترون و ذرات به روش مونت کارلو	ارزیابی دوز پرتو
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1949	1928
پدیدآور	Nicholas Metropolis, Stanislaw Ulam	International Commission on Radiological Protection (ICRP)
نوع	probabilistic computational method	computational health assessment pipeline
منبع بنیادین	Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341.	International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4).
نام‌های دیگر	Monte Carlo simulation, stochastic transport, particle history method	dose calculation, exposure assessment, radiation hazard evaluation
مرتبط	5	5
خلاصه	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 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.