Author:
Zhuang Kun,Shang Wen,Li Ting,Yan Jiangtao,Wang Sipeng,Tang Xiaobin,Li Yunzhao
Funder
Jiangsu Province Postdoctoral Science Foundation
China Postdoctoral Science Foundation
Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China
Fundamental Research Funds for the Central Universities
Subject
Nuclear Energy and Engineering
Reference55 articles.
1. Carlson, B.G., Bell, G.I. 1958. Solution of the transport equation by the Sn method. Los Alamos Scientific Lab, N. Mex.
2. A Method for Calculating Collision Probabilities in General Cylindrical Geometry and Applications to Flux Distributions and Dancoff Factors;Carlvik,1964
3. Unifying via conformal mapping coarse-mesh neutron diffusion calculations in Cartesian and hexagonal geometries;Chao;J. Comput. Appl. Math.,1995
4. A new high-fidelity neutronics code NECP-X;Chen;Ann. Nucl. Energy,2018
5. Extension of analytic function expansion nodal method to multigroup problems in hexagonal-Z geometry;Cho;Nucl. Sci. Eng.,1997
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