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] |
| Copyright of Journal of Computational & Theoretical Transport is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.) | |
| Database: | Engineering Source |
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| Header | DbId: egs DbLabel: Engineering Source An: 193490151 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: An Approximation to the Solution of the Transport Equation and Calculation of Diffusion Lengths in Multiplying Media. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Yaşa%2C+Faruk%22">Yaşa, Faruk</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> fyasa@ksu.edu.tr</i> – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Journal+of+Computational+%26+Theoretical+Transport%22">Journal of Computational & Theoretical Transport</searchLink>. 2026, Vol. 55 Issue 2, p190-199. 10p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Transport+equation%22">Transport equation</searchLink><br /><searchLink fieldCode="DE" term="%22Neutron+diffusion%22">Neutron diffusion</searchLink><br /><searchLink fieldCode="DE" term="%22Scattering+%28Physics%29%22">Scattering (Physics)</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+fuels%22">Nuclear fuels</searchLink><br /><searchLink fieldCode="DE" term="%22Legendre's+polynomials%22">Legendre's polynomials</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+fission%22">Nuclear fission</searchLink><br /><searchLink fieldCode="DE" term="%22Neutron+scattering%22">Neutron scattering</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: 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] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Journal of Computational & Theoretical Transport is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.) |
| PLink | https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=egs&AN=193490151 |
| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1080/23324309.2026.2622949 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 10 StartPage: 190 Subjects: – SubjectFull: Transport equation Type: general – SubjectFull: Neutron diffusion Type: general – SubjectFull: Scattering (Physics) Type: general – SubjectFull: Nuclear fuels Type: general – SubjectFull: Legendre's polynomials Type: general – SubjectFull: Nuclear fission Type: general – SubjectFull: Neutron scattering Type: general Titles: – TitleFull: An Approximation to the Solution of the Transport Equation and Calculation of Diffusion Lengths in Multiplying Media. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Yaşa, Faruk IsPartOfRelationships: – BibEntity: Dates: – D: 01 M: 03 Text: 2026 Type: published Y: 2026 Identifiers: – Type: issn-print Value: 23324309 Numbering: – Type: volume Value: 55 – Type: issue Value: 2 Titles: – TitleFull: Journal of Computational & Theoretical Transport Type: main |
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