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

Detalhes bibliográficos
Autor(a) principal: GOMES, DANIEL de S.
Data de Publicação: 2022
Outros Autores: GIOVEDI, CLAUDIA, INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 26th
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/32912
Resumo: The 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.
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spelling 2022-03-30T19:16:28Z2022-03-30T19:16:28ZNovember 22-26, 2021http://repositorio.ipen.br/handle/123456789/32912The 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.Submitted by Pedro Silva Filho (pfsilva@ipen.br) on 2022-03-30T19:16:28Z No. of bitstreams: 1 28629.pdf: 714300 bytes, checksum: ccfb3a97b256d43057f31818408ab6f4 (MD5)Made available in DSpace on 2022-03-30T19:16:28Z (GMT). No. of bitstreams: 1 28629.pdf: 714300 bytes, checksum: ccfb3a97b256d43057f31818408ab6f4 (MD5)Associa????o Brasileira de Engenharia e Ci??ncias Mec??nicas - ABCMfuelsstainless steelskanthalcladdingaccident-tolerant nuclear fuelszircaloyAssessment of advanced ferritic alloys used as cladding materials in nuclear power reactorsinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectCOBEMIRio de Janeiro, RJOnline7670600GOMES, DANIEL de S.GIOVEDI, CLAUDIAINTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 26thinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN286292021GOMES, DANIEL de S.22-03Proceedings7670GOMES, DANIEL de S.:7670:420:SLICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/32912/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52ORIGINAL28629.pdf28629.pdfapplication/pdf714300http://repositorio.ipen.br/bitstream/123456789/32912/1/28629.pdfccfb3a97b256d43057f31818408ab6f4MD51123456789/329122022-05-03 12:50:22.521oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102022-05-03T12:50:22Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
title Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
spellingShingle Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
GOMES, DANIEL de S.
fuels
stainless steels
kanthal
cladding
accident-tolerant nuclear fuels
zircaloy
title_short Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
title_full Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
title_fullStr Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
title_full_unstemmed Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
title_sort Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
author GOMES, DANIEL de S.
author_facet GOMES, DANIEL de S.
GIOVEDI, CLAUDIA
INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 26th
author_role author
author2 GIOVEDI, CLAUDIA
INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 26th
author2_role author
author
dc.contributor.author.fl_str_mv GOMES, DANIEL de S.
GIOVEDI, CLAUDIA
INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 26th
dc.subject.por.fl_str_mv fuels
stainless steels
kanthal
cladding
accident-tolerant nuclear fuels
zircaloy
topic fuels
stainless steels
kanthal
cladding
accident-tolerant nuclear fuels
zircaloy
description The 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.
publishDate 2022
dc.date.evento.pt_BR.fl_str_mv November 22-26, 2021
dc.date.accessioned.fl_str_mv 2022-03-30T19:16:28Z
dc.date.available.fl_str_mv 2022-03-30T19:16:28Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
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dc.identifier.uri.fl_str_mv http://repositorio.ipen.br/handle/123456789/32912
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dc.relation.authority.fl_str_mv 7670
dc.relation.confidence.fl_str_mv 600
dc.rights.driver.fl_str_mv info:eu-repo/semantics/openAccess
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dc.publisher.none.fl_str_mv Associa????o Brasileira de Engenharia e Ci??ncias Mec??nicas - ABCM
publisher.none.fl_str_mv Associa????o Brasileira de Engenharia e Ci??ncias Mec??nicas - ABCM
dc.source.none.fl_str_mv reponame:Repositório Institucional do IPEN
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