Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario

Detalhes bibliográficos
Autor(a) principal: GIOVEDI, CLAUDIA
Data de Publicação: 2018
Outros Autores: ABE, ALFREDO, MUNIZ, RAFAEL O.R., GOMES, DANIEL de S., SILVA, ANTONIO T. e, MARTINS, MARCELO R., INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/28187
Resumo: Accident tolerant fuels (ATF) has been studied since the Fukushima Daiichi accident in the research efforts to develop new materials which under accident scenarios could maintain the fuel rod integrity for a longer period compared to the cladding and fuel system usually utilized in Pressurized Water Reactors (PWR). The efforts have been focused on new materials applied as cladding, then iron-base alloys appear as a possible candidate. The aim of this paper is to implement modifications in a fuel performance code to evaluate the behavior of ironbased alloys under Loss-of-Coolant Accident (LOCA) scenario. For this, initially the properties related to the thermal and mechanical behavior of iron-based alloys were obtained from the literature, appropriately adapted and introduced in the fuel performance code subroutines. The adopted approach was step by step modifications, where different versions of the code were created. The assessment of the implemented modification was carried out simulating an experiment available in the open literature (IFA-650.5) related to zirconium-based alloy fuel rods submitted to LOCA conditions. The obtained results for the iron-based alloy were compared to those obtained using the regular version of the fuel performance code for zircaloy-4. The obtained results have shown that the most important properties to be changed are those from the subroutines related to the mechanical properties of the cladding. The results obtained have shown that the burst is observed at a longer time for fuel rods with iron-based alloy, indicating the potentiality of this material to be used as cladding with ATF purposes.
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spelling 2018-01-02T12:39:13Z2018-01-02T12:39:13ZOctober 22-27, 2017http://repositorio.ipen.br/handle/123456789/28187Accident tolerant fuels (ATF) has been studied since the Fukushima Daiichi accident in the research efforts to develop new materials which under accident scenarios could maintain the fuel rod integrity for a longer period compared to the cladding and fuel system usually utilized in Pressurized Water Reactors (PWR). The efforts have been focused on new materials applied as cladding, then iron-base alloys appear as a possible candidate. The aim of this paper is to implement modifications in a fuel performance code to evaluate the behavior of ironbased alloys under Loss-of-Coolant Accident (LOCA) scenario. For this, initially the properties related to the thermal and mechanical behavior of iron-based alloys were obtained from the literature, appropriately adapted and introduced in the fuel performance code subroutines. The adopted approach was step by step modifications, where different versions of the code were created. The assessment of the implemented modification was carried out simulating an experiment available in the open literature (IFA-650.5) related to zirconium-based alloy fuel rods submitted to LOCA conditions. The obtained results for the iron-based alloy were compared to those obtained using the regular version of the fuel performance code for zircaloy-4. The obtained results have shown that the most important properties to be changed are those from the subroutines related to the mechanical properties of the cladding. The results obtained have shown that the burst is observed at a longer time for fuel rods with iron-based alloy, indicating the potentiality of this material to be used as cladding with ATF purposes.Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2018-01-02T12:39:13Z No. of bitstreams: 1 24012.pdf: 1159936 bytes, checksum: 628e1a77e69210b57e8fbd1915c74253 (MD5)Made available in DSpace on 2018-01-02T12:39:13Z (GMT). No. of bitstreams: 1 24012.pdf: 1159936 bytes, checksum: 628e1a77e69210b57e8fbd1915c74253 (MD5)Associa????o Brasileira de Energia Nuclearaccident-tolerant nuclear fuelscladdingcomputerized simulationf codesfuel rodsiron alloysloss of coolantperformancepwr type reactorsstainless steel-348Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenarioinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de Janeiro, RJBelo Horizonte, MGGIOVEDI, CLAUDIAABE, ALFREDOMUNIZ, RAFAEL O.R.GOMES, DANIEL de S.SILVA, ANTONIO T. eMARTINS, MARCELO R.INTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN240122017ABE, ALFREDOMUNIZ, RAFAEL O.R.GOMES, DANIEL de S.SILVA, ANTONIO T. e18-01Proceedings7817348776701085ABE, ALFREDO:7817:-1:NMUNIZ, RAFAEL O.R.:3487:420:NGOMES, DANIEL DE S.:7670:420:NSILVA, ANTONIO T. E:1085:420:NORIGINAL24012.pdf24012.pdfapplication/pdf1159936http://repositorio.ipen.br/bitstream/123456789/28187/1/24012.pdf628e1a77e69210b57e8fbd1915c74253MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/28187/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/281872022-08-05 17:09:36.291oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102022-08-05T17:09:36Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
title Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
spellingShingle Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
GIOVEDI, CLAUDIA
accident-tolerant nuclear fuels
cladding
computerized simulation
f codes
fuel rods
iron alloys
loss of coolant
performance
pwr type reactors
stainless steel-348
title_short Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
title_full Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
title_fullStr Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
title_full_unstemmed Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
title_sort Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
author GIOVEDI, CLAUDIA
author_facet GIOVEDI, CLAUDIA
ABE, ALFREDO
MUNIZ, RAFAEL O.R.
GOMES, DANIEL de S.
SILVA, ANTONIO T. e
MARTINS, MARCELO R.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author_role author
author2 ABE, ALFREDO
MUNIZ, RAFAEL O.R.
GOMES, DANIEL de S.
SILVA, ANTONIO T. e
MARTINS, MARCELO R.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author2_role author
author
author
author
author
author
dc.contributor.author.fl_str_mv GIOVEDI, CLAUDIA
ABE, ALFREDO
MUNIZ, RAFAEL O.R.
GOMES, DANIEL de S.
SILVA, ANTONIO T. e
MARTINS, MARCELO R.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.subject.por.fl_str_mv accident-tolerant nuclear fuels
cladding
computerized simulation
f codes
fuel rods
iron alloys
loss of coolant
performance
pwr type reactors
stainless steel-348
topic accident-tolerant nuclear fuels
cladding
computerized simulation
f codes
fuel rods
iron alloys
loss of coolant
performance
pwr type reactors
stainless steel-348
description Accident tolerant fuels (ATF) has been studied since the Fukushima Daiichi accident in the research efforts to develop new materials which under accident scenarios could maintain the fuel rod integrity for a longer period compared to the cladding and fuel system usually utilized in Pressurized Water Reactors (PWR). The efforts have been focused on new materials applied as cladding, then iron-base alloys appear as a possible candidate. The aim of this paper is to implement modifications in a fuel performance code to evaluate the behavior of ironbased alloys under Loss-of-Coolant Accident (LOCA) scenario. For this, initially the properties related to the thermal and mechanical behavior of iron-based alloys were obtained from the literature, appropriately adapted and introduced in the fuel performance code subroutines. The adopted approach was step by step modifications, where different versions of the code were created. The assessment of the implemented modification was carried out simulating an experiment available in the open literature (IFA-650.5) related to zirconium-based alloy fuel rods submitted to LOCA conditions. The obtained results for the iron-based alloy were compared to those obtained using the regular version of the fuel performance code for zircaloy-4. The obtained results have shown that the most important properties to be changed are those from the subroutines related to the mechanical properties of the cladding. The results obtained have shown that the burst is observed at a longer time for fuel rods with iron-based alloy, indicating the potentiality of this material to be used as cladding with ATF purposes.
publishDate 2018
dc.date.evento.pt_BR.fl_str_mv October 22-27, 2017
dc.date.accessioned.fl_str_mv 2018-01-02T12:39:13Z
dc.date.available.fl_str_mv 2018-01-02T12:39:13Z
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/123456789/28187
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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 Energia Nuclear
publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
dc.source.none.fl_str_mv reponame:Repositório Institucional do IPEN
instname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)
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institution IPEN
reponame_str Repositório Institucional do IPEN
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