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- [3] COMPARISON OF NEUTRON-ATTENUATION CALCULATIONS USING MONTE CARLO TRANSPORT AND DIFFUSION-THEORY METHODS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1965, 8 (01): : 188 - &
- [5] Analysis of Accuracy and Efficiency of Two Node Method for Solving Fine Mesh SP3 Neutron Transport Equations Hedongli Gongcheng/Nuclear Power Engineering, 2020, 41 (02): : 184 - 188