An Approximation to the Solution of the Transport Equation and Calculation of Diffusion Lengths in Multiplying Media.
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| Title: | An Approximation to the Solution of the Transport Equation and Calculation of Diffusion Lengths in Multiplying Media. |
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| Authors: | Yaşa, Faruk1 (AUTHOR) fyasa@ksu.edu.tr |
| Source: | Journal of Computational & Theoretical Transport. 2026, Vol. 55 Issue 2, p190-199. 10p. |
| Subjects: | Transport equation, Neutron diffusion, Scattering (Physics), Nuclear fuels, Legendre's polynomials, Nuclear fission, Neutron scattering |
| Abstract: | Various anisotropic scattering kernels are presented to solve the transport equation in multiplying media, and calculations are also performed for the isotropic scattering case and the non-multiplying medium to enable a meaningful comparison. Henyey–Greenstein-like scattering kernel is employed to model anisotropic scattering of neutrons. The effect of anisotropic scattering on the diffusion length of a multiplying slab is investigated using the Legendre polynomial expansion method. A comprehensive numerical analysis of diffusion lengths was performed to represent the fuel system in a nuclear reactor. [ABSTRACT FROM AUTHOR] |
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| Database: | Engineering Source |
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| Abstract: | Various anisotropic scattering kernels are presented to solve the transport equation in multiplying media, and calculations are also performed for the isotropic scattering case and the non-multiplying medium to enable a meaningful comparison. Henyey–Greenstein-like scattering kernel is employed to model anisotropic scattering of neutrons. The effect of anisotropic scattering on the diffusion length of a multiplying slab is investigated using the Legendre polynomial expansion method. A comprehensive numerical analysis of diffusion lengths was performed to represent the fuel system in a nuclear reactor. [ABSTRACT FROM AUTHOR] |
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| ISSN: | 23324309 |
| DOI: | 10.1080/23324309.2026.2622949 |
