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| Thiết kế che chắn 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≠ | 1898 | 1949 |
| Người khởi xướng≠ | Ernest Rutherford, Pierre Curie | Nicholas Metropolis, Stanislaw Ulam |
| Loại≠ | engineering design methodology | probabilistic computational method |
| Công trình gốc≠ | Cember, H., & Johnson, T. E. (2009). Introduction to Health Physics (4th ed.). McGraw-Hill. link ↗ | Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗ |
| Tên gọi khác | shield analysis, attenuation design, dose reduction engineering | Monte Carlo simulation, stochastic transport, particle history method |
| Liên quan | 5 | 5 |
| Tóm tắt≠ | Radiation shielding design is an engineering discipline that uses physics-based calculations and materials selection to reduce radiation exposure to acceptable levels, originating from Curie and Rutherford's early radiation studies in the 1890s. By combining attenuation theory, source characterization, and dose modeling, it determines material composition, thickness, and geometry to protect workers, the public, and sensitive equipment. | 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. |
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