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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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dc.citation.endPage 54 -
dc.citation.number 1 -
dc.citation.startPage 46 -
dc.citation.title NUCLEAR SCIENCE AND ENGINEERING -
dc.citation.volume 151 -
dc.contributor.author Lee, Deokjung -
dc.contributor.author Lee, H.C. -
dc.contributor.author Downar, T.J -
dc.date.accessioned 2023-12-22T10:13:35Z -
dc.date.available 2023-12-22T10:13:35Z -
dc.date.created 2014-10-17 -
dc.date.issued 2005-09 -
dc.description.abstract Two methods are proposed for solving the three-dimensional neutron diffusion equation by iterating between solutions of the two-dimensional (2-D) radial and one-dimensional (1-D) axial solutions. In the first method, the 2-D/1-D equations are coupled using a current correction factor (CCF) with the average fluxes of the lower and upper planes and the axial net currents at the plane interfaces. In the second method, an analytic expression for the axial net currents at the interface of the planes is used for planar coupling. A comparison of the new methods is made with two previously proposed methods, which use interface net currents and partial currents for planar coupling. A Fourier convergence analysis of the four methods was performed, and results indicate that the two new methods have at least three advantages over the previous methods. First, the new methods are unconditionally stable, whereas the net current method diverges for small axial mesh size. Second, the new methods provide better convergence performance than the other methods in the range of practical mesh sizes. Third, the spectral radii of the new methods asymptotically approach zero as the mesh size increases, while the spectral radius of the partial current method approaches a nonzero value as the mesh size increases. Of the two new methods proposed here, the analytic method provides a smaller spectral radius than the CCF method, but the CCF method has several advantages over the analytic method in practical applications. -
dc.identifier.bibliographicCitation NUCLEAR SCIENCE AND ENGINEERING, v.151, no.1, pp.46 - 54 -
dc.identifier.issn 0029-5639 -
dc.identifier.scopusid 2-s2.0-24744467609 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/7401 -
dc.identifier.url http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=24744467609 -
dc.identifier.wosid 000231518100003 -
dc.language 영어 -
dc.publisher AMER NUCLEAR SOCIETY -
dc.title Iterative two- and one-dimensional methods for three-dimensional neutron diffusion calculations -
dc.type Article -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordPlus FUNCTION EXPANSION -
dc.subject.keywordPlus EQUATIONS -
dc.subject.keywordPlus GEOMETRY -
dc.subject.keywordPlus FORMULATION -

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