विधियों की तुलना करें

	विकिरण खुराक मूल्यांकन	Monte Carlo न्यूट्रॉन और कण परिवहन (Monte Carlo Neutron & Particle Transport)
क्षेत्र	नाभिकीय भौतिकी	नाभिकीय भौतिकी
परिवार	Process / pipeline	Process / pipeline
उद्भव वर्ष	1928	1949
प्रवर्तक	International Commission on Radiological Protection (ICRP)	Nicholas Metropolis, Stanislaw Ulam
प्रकार	computational health assessment pipeline	probabilistic computational method
मौलिक स्रोत	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.
उपनाम	dose calculation, exposure assessment, radiation hazard evaluation	Monte Carlo simulation, stochastic transport, particle history method
संबंधित	5	5
सारांश	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.