Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors

Página do item simplificado
dc.contributor.authorGOMES, DANIEL de S.pt_BR
dc.contributor.authorGIOVEDI, CLAUDIApt_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 26thpt_BR
dc.date.accessioned2022-03-30T19:16:28Z
dc.date.available2022-03-30T19:16:28Z
dc.date.eventoNovember 22-26, 2021pt_BR
dc.description.abstractThe fuel performance code, Fuel Analysis under Steady-state and Transients (FAST), permits cladding options, such as zirconium alloys and iron-chromium-aluminum (FeCrAl). FAST code support as cladding Kanthal, CM35, and CM36 alloys. We implemented a comparative analysis between ferritic alloys, steel, and zircaloy. Many features of ferritic alloys classify as more tolerant materials, such as high resistance to steam oxidation, reduced hydrogen release, and longer coping time. But the neutron penalty must reduce cladding thickness to let a greater fuel volume. Both ferritic alloys and austenitic steel show higher corrosion resistance, also avoiding hydrogen releases. FeCrAl provides more resistant corrosion cracking than stainless steel. The properties of steel 348 are comparable to those of FeCrAl alloys. Steel exhibits superior thermal conductivity, linear thermal expansion, and mechanical strength. Both offer similar specific heat, melting points, and densities. The chemical composition of the steel has 66% iron and 19% chromium, compared with Kanthal APMT™, which uses 68.8% iron and 22% chromium. The results found real advantages related to safety risks using ferritic cladding materials.pt_BR
dc.event.siglaCOBEMpt_BR
dc.identifier.citationGOMES, DANIEL de S.; GIOVEDI, CLAUDIA. Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors. In: INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 26th, November 22-26, 2021, Online. <b>Proceedings...</b> Rio de Janeiro, RJ: Associação Brasileira de Engenharia e Ciências Mecânicas - ABCM, 2021. Disponível em: http://repositorio.ipen.br/handle/123456789/32912.
dc.identifier.orcidhttps://orcid.org/0000-0002-2181-8704
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/32912
dc.localRio de Janeiro, RJpt_BR
dc.local.eventoOnlinept_BR
dc.publisherAssociação Brasileira de Engenharia e Ciências Mecânicas - ABCMpt_BR
dc.rightsopenAccesspt_BR
dc.subjectfuels
dc.subjectstainless steels
dc.subjectkanthal
dc.subjectcladding
dc.subjectaccident-tolerant nuclear fuels
dc.subjectzircaloy
dc.titleAssessment of advanced ferritic alloys used as cladding materials in nuclear power reactorspt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorDANIEL DE SOUZA GOMES
ipen.codigoautor7670
ipen.contributor.ipenauthorDANIEL DE SOUZA GOMES
ipen.date.recebimento22-03
ipen.event.datapadronizada2021pt_BR
ipen.identifier.ipendoc28629pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublication090e1d1e-dfb3-4120-8d6f-1374e82feb2b
relation.isAuthorOfPublication.latestForDiscovery090e1d1e-dfb3-4120-8d6f-1374e82feb2b
sigepi.autor.atividadeGOMES, DANIEL de S.:7670:420:Spt_BR
Pacote Original
Agora exibindo 1 - 1 de 1
Imagem de Miniatura
Nome:
28629.pdf
Tamanho:
697.56 KB
Formato:
Adobe Portable Document Format
Descrição:
Baixar
Licença do Pacote
Agora exibindo 1 - 1 de 1
Nenhuma Miniatura disponível
Nome:
license.txt
Tamanho:
1.71 KB
Formato:
Item-specific license agreed upon to submission
Descrição:
Baixar
Coleções
Eventos