Generation of leading coefficients of orthogonal polynomials with an application to anisotropic scattering of neutrons
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference3 articles.
1. Accurate Evaluation of Multigroup Transfer Cross Sections and Their Legendre Coefficients
2. The Slowing Down and Thermalization of Neutrons;Williams,1966
Cited by 4 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. Analytical Method for Processing Neutron Multigroup Transfer Cross Sections;Nuclear Science and Engineering;1992-08
2. Power series expansion of the neutron scattering transformation matrix: The A < 1 case;Annals of Nuclear Energy;1991-01
3. On the neutron scattering transformation matrices;Annals of Nuclear Energy;1987-01
4. A new method for the evaluation of neutron elastic transformation matrices;Annals of Nuclear Energy;1984-01
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