Analysis of the physical models used for nuclear ceramic fuel

dc.contributor.authorGOMES, D.S.
dc.contributor.editorOLIVEIRA, ANTONELLA C. de
dc.contributor.organizadorHOLZMANN, HENRIQUE A.
dc.contributor.organizadorBILCATI, GÉSSICA K.
dc.coverageNacional
dc.date.accessioned2024-12-12T18:25:19Z
dc.date.available2024-12-12T18:25:19Z
dc.date.issued2024
dc.description.abstractNuclear ceramics resist to radiation exposure and may change their thermal and mechanical properties. Many ceramic fuels, such as UO2 and mixed oxide (MOX), are the primary fuels used in the current commercial light water reactors. Fusion reactor use of low-activity ceramics, primarily silicon carbide, will eliminate the generation of large quantities of highly radioactive waste. Silicon carbides show desirable mechanical properties and corrosion resistance at high temperatures, making them essential for nuclear fuel cladding intended for a vast range of fuels in LWRs, Gas-cooled reactors use TRISO fuel at high temperatures. Generation IV reactors scheduled for 2035 have defined seven reactor types that will operate at higher temperatures with extended burn cycles, employing innovative fuels focusing on carbide UC and nitride UN. A review of the thermal and mechanical models used in the FRAPCON codes is presented.
dc.format.extent248-258
dc.identifier.capitulo18
dc.identifier.citationGOMES, D.S. Analysis of the physical models used for nuclear ceramic fuel. In: OLIVEIRA, ANTONELLA C. de (ed.); HOLZMANN, HENRIQUE A. (org.); BILCATI, GÉSSICA K. (org.). <b>Engenharias: desafios e soluções nas múltiplas fronteiras do conhecimento</b>. Ponta Grossa, PR: Atena, 2024. , cap. 18. p. 248-258. DOI: <a href="https://dx.doi.org/10.22533/at.ed.64224240418">10.22533/at.ed.64224240418</a>. Disponível em: https://repositorio.ipen.br/handle/123456789/48763.
dc.identifier.doi10.22533/at.ed.64224240418
dc.identifier.orcidhttps://orcid.org/0000-0002-2181-8704
dc.identifier.urihttps://repositorio.ipen.br/handle/123456789/48763
dc.localPonta Grossa, PR
dc.publisherAtena
dc.rightsopenAccess
dc.titleAnalysis of the physical models used for nuclear ceramic fuel
dc.title.livroEngenharias: desafios e soluções nas múltiplas fronteiras do conhecimento
dc.typeCapítulo de livro
dspace.entity.typePublication
ipen.autorDANIEL DE SOUZA GOMES
ipen.codigoautor7670
ipen.contributor.ipenauthorDANIEL DE SOUZA GOMES
ipen.identifier.ipendoc30880
ipen.type.genreCapítulo
relation.isAuthorOfPublication090e1d1e-dfb3-4120-8d6f-1374e82feb2b
relation.isAuthorOfPublication.latestForDiscovery090e1d1e-dfb3-4120-8d6f-1374e82feb2b
sigepi.autor.atividadeDANIEL DE SOUZA GOMES:7670:420:N

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