So sánh phương pháp

	Đánh giá liều bức xạ	Vận chuyển Neutron & Hạt Monte Carlo
Lĩnh vực	Vật lý hạt nhân	Vật lý hạt nhân
Họ	Process / pipeline	Process / pipeline
Năm ra đời	1928	1949
Người khởi xướng	International Commission on Radiological Protection (ICRP)	Nicholas Metropolis, Stanislaw Ulam
Loại	computational health assessment pipeline	probabilistic computational method
Công trình gốc	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.
Tên gọi khác	dose calculation, exposure assessment, radiation hazard evaluation	Monte Carlo simulation, stochastic transport, particle history method
Liên quan	5	5
Tóm tắt	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.