Sensitivity assessment of fuel performance codes for loca accident scenario
Autor(a) principal: | |
---|---|
Data de Publicação: | 2018 |
Outros Autores: | , , , , , |
Tipo de documento: | Artigo de conferência |
Título da fonte: | Repositório Institucional do IPEN |
Texto Completo: | http://repositorio.ipen.br/handle/123456789/28196 |
Resumo: | FRAPCON code predicts fuel rod performance in LWR (Light Water Reactor) by modeling fuel responses under normal operating conditions and anticipated operational occurrences; FRAPTRAN code is applied for fuel transient under fast transient and accident conditions. The codes are well known and applied for different purposes and one of the use is to address sensitivity analysis considering fuel design parameters associated to fabrication, moreover can address the effect of physical models bias. The objective of this work was to perform an assessment of fuel manufacturing parameters tolerances and fuel models bias using FRAPCON and FRAPTRAN codes for Loss of Coolant Accident (LOCA) scenario. The preliminary analysis considered direct approach taken into account most relevant manufacturing tolerances (lower and upper bounds) related to design parameters and physical models bias without considering their statistical distribution. The simulations were carried out using the data available in the open literature related to the series of LOCA experiment performed at the Halden reactor (specifically IFA-650.5). The manufacturing tolerances associated to design parameters considered in this paper were: enrichment, cladding thickness, pellet diameter, pellet density, and filling gas pressure. The physical models considered were: fuel thermal expansion, fission gas release, fuel swelling, irradiation creep, cladding thermal expansion, cladding corrosion, and cladding hydrogen pickup. The results obtained from sensitivity analysis addressed the impact of manufacturing tolerances and physical models in the fuel cladding burst time observed for the IFA-650.5 experiment. |
id |
IPEN_8ad5aecbf199e94ad557562620645e07 |
---|---|
oai_identifier_str |
oai:repositorio.ipen.br:123456789/28196 |
network_acronym_str |
IPEN |
network_name_str |
Repositório Institucional do IPEN |
repository_id_str |
4510 |
spelling |
2018-01-02T17:52:00Z2018-01-02T17:52:00ZOctober 22-27, 2017http://repositorio.ipen.br/handle/123456789/28196FRAPCON code predicts fuel rod performance in LWR (Light Water Reactor) by modeling fuel responses under normal operating conditions and anticipated operational occurrences; FRAPTRAN code is applied for fuel transient under fast transient and accident conditions. The codes are well known and applied for different purposes and one of the use is to address sensitivity analysis considering fuel design parameters associated to fabrication, moreover can address the effect of physical models bias. The objective of this work was to perform an assessment of fuel manufacturing parameters tolerances and fuel models bias using FRAPCON and FRAPTRAN codes for Loss of Coolant Accident (LOCA) scenario. The preliminary analysis considered direct approach taken into account most relevant manufacturing tolerances (lower and upper bounds) related to design parameters and physical models bias without considering their statistical distribution. The simulations were carried out using the data available in the open literature related to the series of LOCA experiment performed at the Halden reactor (specifically IFA-650.5). The manufacturing tolerances associated to design parameters considered in this paper were: enrichment, cladding thickness, pellet diameter, pellet density, and filling gas pressure. The physical models considered were: fuel thermal expansion, fission gas release, fuel swelling, irradiation creep, cladding thermal expansion, cladding corrosion, and cladding hydrogen pickup. The results obtained from sensitivity analysis addressed the impact of manufacturing tolerances and physical models in the fuel cladding burst time observed for the IFA-650.5 experiment.Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2018-01-02T17:52:00Z No. of bitstreams: 1 24021.pdf: 354429 bytes, checksum: f45a55ddc6dd8a1d29fab349ce371504 (MD5)Made available in DSpace on 2018-01-02T17:52:00Z (GMT). No. of bitstreams: 1 24021.pdf: 354429 bytes, checksum: f45a55ddc6dd8a1d29fab349ce371504 (MD5)Associa????o Brasileira de Energia Nuclearaccident-tolerant nuclear fuelscomputerized simulationf codesfuel rodsfuel-cladding interactionsloss of coolantsensitivity analysistransientswater cooled reactorsSensitivity assessment of fuel performance codes for loca accident scenarioinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de Janeiro, RJBelo Horizonte, MGABE, ALFREDOGIOVEDI, CLAUDIAGOMES, DANIELSILVA, ANTONIO T. eMUNIZ, RAFAEL O.R.MARTINS, MARCELOINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN240212017ABE, ALFREDOGOMES, DANIELSILVA, ANTONIO T. eMUNIZ, RAFAEL O.R.18-01Proceedings7817767010853487ABE, ALFREDO:7817:-1:SGOMES, DANIEL:7670:420:NSILVA, ANTONIO T. E:1085:420:NMUNIZ, RAFAEL O.R.:3487:420:NORIGINAL24021.pdf24021.pdfapplication/pdf354429http://repositorio.ipen.br/bitstream/123456789/28196/1/24021.pdff45a55ddc6dd8a1d29fab349ce371504MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/28196/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/281962022-08-05 17:11:14.07oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102022-08-05T17:11:14Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false |
dc.title.pt_BR.fl_str_mv |
Sensitivity assessment of fuel performance codes for loca accident scenario |
title |
Sensitivity assessment of fuel performance codes for loca accident scenario |
spellingShingle |
Sensitivity assessment of fuel performance codes for loca accident scenario ABE, ALFREDO accident-tolerant nuclear fuels computerized simulation f codes fuel rods fuel-cladding interactions loss of coolant sensitivity analysis transients water cooled reactors |
title_short |
Sensitivity assessment of fuel performance codes for loca accident scenario |
title_full |
Sensitivity assessment of fuel performance codes for loca accident scenario |
title_fullStr |
Sensitivity assessment of fuel performance codes for loca accident scenario |
title_full_unstemmed |
Sensitivity assessment of fuel performance codes for loca accident scenario |
title_sort |
Sensitivity assessment of fuel performance codes for loca accident scenario |
author |
ABE, ALFREDO |
author_facet |
ABE, ALFREDO GIOVEDI, CLAUDIA GOMES, DANIEL SILVA, ANTONIO T. e MUNIZ, RAFAEL O.R. MARTINS, MARCELO INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author_role |
author |
author2 |
GIOVEDI, CLAUDIA GOMES, DANIEL SILVA, ANTONIO T. e MUNIZ, RAFAEL O.R. MARTINS, MARCELO INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author2_role |
author author author author author author |
dc.contributor.author.fl_str_mv |
ABE, ALFREDO GIOVEDI, CLAUDIA GOMES, DANIEL SILVA, ANTONIO T. e MUNIZ, RAFAEL O.R. MARTINS, MARCELO INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
dc.subject.por.fl_str_mv |
accident-tolerant nuclear fuels computerized simulation f codes fuel rods fuel-cladding interactions loss of coolant sensitivity analysis transients water cooled reactors |
topic |
accident-tolerant nuclear fuels computerized simulation f codes fuel rods fuel-cladding interactions loss of coolant sensitivity analysis transients water cooled reactors |
description |
FRAPCON code predicts fuel rod performance in LWR (Light Water Reactor) by modeling fuel responses under normal operating conditions and anticipated operational occurrences; FRAPTRAN code is applied for fuel transient under fast transient and accident conditions. The codes are well known and applied for different purposes and one of the use is to address sensitivity analysis considering fuel design parameters associated to fabrication, moreover can address the effect of physical models bias. The objective of this work was to perform an assessment of fuel manufacturing parameters tolerances and fuel models bias using FRAPCON and FRAPTRAN codes for Loss of Coolant Accident (LOCA) scenario. The preliminary analysis considered direct approach taken into account most relevant manufacturing tolerances (lower and upper bounds) related to design parameters and physical models bias without considering their statistical distribution. The simulations were carried out using the data available in the open literature related to the series of LOCA experiment performed at the Halden reactor (specifically IFA-650.5). The manufacturing tolerances associated to design parameters considered in this paper were: enrichment, cladding thickness, pellet diameter, pellet density, and filling gas pressure. The physical models considered were: fuel thermal expansion, fission gas release, fuel swelling, irradiation creep, cladding thermal expansion, cladding corrosion, and cladding hydrogen pickup. The results obtained from sensitivity analysis addressed the impact of manufacturing tolerances and physical models in the fuel cladding burst time observed for the IFA-650.5 experiment. |
publishDate |
2018 |
dc.date.evento.pt_BR.fl_str_mv |
October 22-27, 2017 |
dc.date.accessioned.fl_str_mv |
2018-01-02T17:52:00Z |
dc.date.available.fl_str_mv |
2018-01-02T17:52:00Z |
dc.type.status.fl_str_mv |
info:eu-repo/semantics/publishedVersion |
dc.type.driver.fl_str_mv |
info:eu-repo/semantics/conferenceObject |
format |
conferenceObject |
status_str |
publishedVersion |
dc.identifier.uri.fl_str_mv |
http://repositorio.ipen.br/handle/123456789/28196 |
url |
http://repositorio.ipen.br/handle/123456789/28196 |
dc.rights.driver.fl_str_mv |
info:eu-repo/semantics/openAccess |
eu_rights_str_mv |
openAccess |
dc.coverage.pt_BR.fl_str_mv |
I |
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) instacron:IPEN |
instname_str |
Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
instacron_str |
IPEN |
institution |
IPEN |
reponame_str |
Repositório Institucional do IPEN |
collection |
Repositório Institucional do IPEN |
bitstream.url.fl_str_mv |
http://repositorio.ipen.br/bitstream/123456789/28196/1/24021.pdf http://repositorio.ipen.br/bitstream/123456789/28196/2/license.txt |
bitstream.checksum.fl_str_mv |
f45a55ddc6dd8a1d29fab349ce371504 8a4605be74aa9ea9d79846c1fba20a33 |
bitstream.checksumAlgorithm.fl_str_mv |
MD5 MD5 |
repository.name.fl_str_mv |
Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
repository.mail.fl_str_mv |
bibl@ipen.br |
_version_ |
1767254242835300352 |