So sánh phương pháp

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