Title: Comparison of transport and diffusion theory for fast reactor shielding calculations
Abstract:The use of diffusion theory for fast reactor shielding calculations in complex and thick configurations is questionable and it is necessary to apply transport theory to correctly solve this kind of pr...The use of diffusion theory for fast reactor shielding calculations in complex and thick configurations is questionable and it is necessary to apply transport theory to correctly solve this kind of problem. Transport calculations are carried out using the one-dimensional SN Code ANISN. Anisotropic scattering cross sections are represented by the P/sub 5/-approximation. Neutron spectra characteristic of the proposed FFTF reactor are assumed as the neutron source and the shield consists of various combinations of iron and sodium. (GE)Read More
Publication Year: 1973
Publication Date: 1973-09-01
Language: en
Type: article
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Cited By Count: 4
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