The Green’s Function Nodal Expansion Method for Light Water Reactor Diffusion Calculations
Author:
Affiliation:
1. Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
2. Xi’an Jiaotong University, Department of Energy and Power Engineering Xi’an, Shaanxi 710049, China
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE95-A24134
Reference9 articles.
1. K. S. SMITH, “An Analytic Nodal Method for Solving the Two Group, Multidimensional, Static and Transient Neutron Diffusion Equations,” MS Thesis, Massachusetts Institute of Technology (1977).
2. A Nodal Green’s Function Method for Multidimensional Neutron Diffusion Calculations
3. A. M. OUGOUAG, “A Coarse-Mesh Nodal Method for Multigroup Multidimensional Neutron Diffusion Computations,” MS Thesis, University of Illinois (1981).
4. A Fundamental Derivation of the Nodal Diffusion Equation and Its Variation
Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. On the better performance of the coarse-mesh finite-difference method for CANDU-type reactors;Annals of Nuclear Energy;2012-08
2. Assessment of the traditional neutron-diffusion core-analysis method for the analysis of the Super Critical Water Reactor;Annals of Nuclear Energy;2012-07
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