Improved lumped model for thermal analysis of high burn-up nuclear fuel rods

Detalhes bibliográficos
Autor(a) principal: Pontedeiro, Auro Correia
Data de Publicação: 2008
Outros Autores: Cotta, Renato Machado, Su, Jian
Tipo de documento: Artigo
Idioma: eng
Título da fonte: Repositório Institucional da UFRJ
Texto Completo: http://hdl.handle.net/11422/8817
Resumo: Indisponível.
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spelling Pontedeiro, Auro CorreiaCotta, Renato MachadoSu, Jian2019-07-15T20:37:37Z2023-11-30T03:01:06Z2008-03-070149-1970http://hdl.handle.net/11422/881710.1016/j.pnucene.2008.01.005Indisponível.High burn-up nuclear fuel elements have been intensively studied for prolonged lifetime of existing reactors and for next-generation advanced reactors. This paper presents an improved lumped-differential formulation for one-dimensional transient heat conduction in a heat generating cylinder with temperature-dependent thermo-physical properties typical of high burn-up nuclear fuel rods. Two-points Hermite approximations for integrals (H1,1/H1,1) were used to obtain the average temperature and heat flux in the radial direction. As a testing case, transient heat conduction in a nuclear fuel rod was computed with the thermo-physical properties represented by the MATPRO correlations. The problem was formulated and solved by using the symbolic/numerical computation software system MATHEMATICA. The solutions of the proposed improved lumped model were validated by comparing with numerical solutions of the original distributed parameter formulation of the transient heat conduction problem, as well as by comparing with simulation results of a cold leg SBLOCA with RELAP5/MOD3.Submitted by Jairo Amaro (jairo.amaro@sibi.ufrj.br) on 2019-07-15T20:37:37Z No. of bitstreams: 1 2008_COTTA_PNE_v50_p767-773-min.pdf: 162373 bytes, checksum: 4cbabacc7e1d3b65e8bc6f4f61de2876 (MD5)Made available in DSpace on 2019-07-15T20:37:37Z (GMT). No. of bitstreams: 1 2008_COTTA_PNE_v50_p767-773-min.pdf: 162373 bytes, checksum: 4cbabacc7e1d3b65e8bc6f4f61de2876 (MD5) Previous issue date: 2008-03-07engElsevierBrasilNúcleo Interdisciplinar de Dinâmica dos FluidosProgress in Nuclear EnergyCNPQ::CIENCIAS EXATAS E DA TERRA::FISICA::AREAS CLASSICAS DE FENOMENOLOGIA E SUAS APLICACOES::DINAMICA DOS FLUIDOSNuclear fuel rodsHigh burn-upTransient heat conductionLumped modelNonlinear diffusion problemImproved lumped model for thermal analysis of high burn-up nuclear fuel rodsinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/article507767773365 diasinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional da UFRJinstname:Universidade Federal do Rio de Janeiro (UFRJ)instacron:UFRJORIGINAL2008_COTTA_PNE_v50_p767-773-min.pdf2008_COTTA_PNE_v50_p767-773-min.pdfapplication/pdf162373http://pantheon.ufrj.br:80/bitstream/11422/8817/1/2008_COTTA_PNE_v50_p767-773-min.pdf4cbabacc7e1d3b65e8bc6f4f61de2876MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81853http://pantheon.ufrj.br:80/bitstream/11422/8817/2/license.txtdd32849f2bfb22da963c3aac6e26e255MD5211422/88172023-11-30 00:01:06.013oai:pantheon.ufrj.br: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Repositório de PublicaçõesPUBhttp://www.pantheon.ufrj.br/oai/requestopendoar:2023-11-30T03:01:06Repositório Institucional da UFRJ - Universidade Federal do Rio de Janeiro (UFRJ)false
dc.title.en.fl_str_mv Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
title Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
spellingShingle Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
Pontedeiro, Auro Correia
CNPQ::CIENCIAS EXATAS E DA TERRA::FISICA::AREAS CLASSICAS DE FENOMENOLOGIA E SUAS APLICACOES::DINAMICA DOS FLUIDOS
Nuclear fuel rods
High burn-up
Transient heat conduction
Lumped model
Nonlinear diffusion problem
title_short Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
title_full Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
title_fullStr Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
title_full_unstemmed Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
title_sort Improved lumped model for thermal analysis of high burn-up nuclear fuel rods
author Pontedeiro, Auro Correia
author_facet Pontedeiro, Auro Correia
Cotta, Renato Machado
Su, Jian
author_role author
author2 Cotta, Renato Machado
Su, Jian
author2_role author
author
dc.contributor.author.fl_str_mv Pontedeiro, Auro Correia
Cotta, Renato Machado
Su, Jian
dc.subject.cnpq.fl_str_mv CNPQ::CIENCIAS EXATAS E DA TERRA::FISICA::AREAS CLASSICAS DE FENOMENOLOGIA E SUAS APLICACOES::DINAMICA DOS FLUIDOS
topic CNPQ::CIENCIAS EXATAS E DA TERRA::FISICA::AREAS CLASSICAS DE FENOMENOLOGIA E SUAS APLICACOES::DINAMICA DOS FLUIDOS
Nuclear fuel rods
High burn-up
Transient heat conduction
Lumped model
Nonlinear diffusion problem
dc.subject.eng.fl_str_mv Nuclear fuel rods
High burn-up
Transient heat conduction
Lumped model
Nonlinear diffusion problem
description Indisponível.
publishDate 2008
dc.date.issued.fl_str_mv 2008-03-07
dc.date.accessioned.fl_str_mv 2019-07-15T20:37:37Z
dc.date.available.fl_str_mv 2023-11-30T03:01:06Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
dc.type.driver.fl_str_mv info:eu-repo/semantics/article
format article
status_str publishedVersion
dc.identifier.uri.fl_str_mv http://hdl.handle.net/11422/8817
dc.identifier.issn.pt_BR.fl_str_mv 0149-1970
dc.identifier.doi.pt_BR.fl_str_mv 10.1016/j.pnucene.2008.01.005
identifier_str_mv 0149-1970
10.1016/j.pnucene.2008.01.005
url http://hdl.handle.net/11422/8817
dc.language.iso.fl_str_mv eng
language eng
dc.relation.ispartof.en.fl_str_mv Progress in Nuclear Energy
dc.rights.driver.fl_str_mv info:eu-repo/semantics/openAccess
eu_rights_str_mv openAccess
dc.publisher.none.fl_str_mv Elsevier
dc.publisher.country.fl_str_mv Brasil
dc.publisher.department.fl_str_mv Núcleo Interdisciplinar de Dinâmica dos Fluidos
publisher.none.fl_str_mv Elsevier
dc.source.none.fl_str_mv reponame:Repositório Institucional da UFRJ
instname:Universidade Federal do Rio de Janeiro (UFRJ)
instacron:UFRJ
instname_str Universidade Federal do Rio de Janeiro (UFRJ)
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reponame_str Repositório Institucional da UFRJ
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bitstream.url.fl_str_mv http://pantheon.ufrj.br:80/bitstream/11422/8817/1/2008_COTTA_PNE_v50_p767-773-min.pdf
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