مقایسهٔ روش‌ها

	بهینه‌سازی حفاظت در برابر پرتوها	حمل و نقل نوترون و ذرات به روش مونت کارلو
حوزه	فیزیک هسته‌ای	فیزیک هسته‌ای
خانواده	Process / pipeline	Process / pipeline
سال پیدایش	1977	1949
پدیدآور	International Commission on Radiological Protection (ICRP)	Nicholas Metropolis, Stanislaw Ulam
نوع	optimization methodology	probabilistic computational method
منبع بنیادین	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.
نام‌های دیگر	ALARA optimization, health physics planning, dose optimization	Monte Carlo simulation, stochastic transport, particle history method
مرتبط	5	5
خلاصه	Radiation protection optimization is a systematic approach to design and manage exposure reduction strategies using risk-benefit analysis, codified by the ICRP in the principle of As Low As Reasonably Achievable (ALARA) in 1977. By balancing radiation dose reduction against cost, effort, and societal benefit, it guides practical protection decisions in medical imaging, occupational settings, and environmental remediation.	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.