Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation

Detalhes bibliográficos
Autor(a) principal: BORGES, EDUARDO M.
Data de Publicação: 2020
Outros Autores: SABUNDJIAN, GAIANE, INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/30728
Resumo: The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 200cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core.
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spelling 2020-01-15T18:35:17Z2020-01-15T18:35:17ZOctober 21-25, 2019http://repositorio.ipen.br/handle/123456789/307280000-0001-9544-4509The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 200cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core.Submitted by Celia Satomi Uehara (celia.u-topservice@ipen.br) on 2020-01-15T18:35:17Z No. of bitstreams: 1 26381.pdf: 1073435 bytes, checksum: f1c302df9241e112e7480fef623a66da (MD5)Made available in DSpace on 2020-01-15T18:35:17Z (GMT). No. of bitstreams: 1 26381.pdf: 1073435 bytes, checksum: f1c302df9241e112e7480fef623a66da (MD5)5479-5490Associa????o Brasileira de Energia Nuclearangra-2 reactorcladdingeccsheat transferprimary coolant circuitsreactor accident simulationreactor coressblocasteady-state conditionstwo-phase flowvoid fractionSmall break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluationinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de JaneiroSantos, SP11597202600600BORGES, EDUARDO M.SABUNDJIAN, GAIANEINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN263812019SABUNDJIAN, GAIANEBORGES, EDUARDO M.20-01Proceedings20211597SABUNDJIAN, GAIANE:202:420:NBORGES, EDUARDO M.:11597:-1:SORIGINAL26381.pdf26381.pdfapplication/pdf1073435http://repositorio.ipen.br/bitstream/123456789/30728/1/26381.pdff1c302df9241e112e7480fef623a66daMD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/30728/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/307282020-04-12 23:11:05.373oai:repositorio.ipen.br:123456789/30728Tk9URTogUExBQ0UgWU9VUiBPV04gTElDRU5TRSBIRVJFClRoaXMgc2FtcGxlIGxpY2Vuc2UgaXMgcHJvdmlkZWQgZm9yIGluZm9ybWF0aW9uYWwgcHVycG9zZXMgb25seS4KCk5PTi1FWENMVVNJVkUgRElTVFJJQlVUSU9OIExJQ0VOU0UKCkJ5IHNpZ25pbmcgYW5kIHN1Ym1pdHRpbmcgdGhpcyBsaWNlbnNlLCB5b3UgKHRoZSBhdXRob3Iocykgb3IgY29weXJpZ2h0Cm93bmVyKSBncmFudHMgdG8gRFNwYWNlIFVuaXZlcnNpdHkgKERTVSkgdGhlIG5vbi1leGNsdXNpdmUgcmlnaHQgdG8gcmVwcm9kdWNlLAp0cmFuc2xhdGUgKGFzIGRlZmluZWQgYmVsb3cpLCBhbmQvb3IgZGlzdHJpYnV0ZSB5b3VyIHN1Ym1pc3Npb24gKGluY2x1ZGluZwp0aGUgYWJzdHJhY3QpIHdvcmxkd2lkZSBpbiBwcmludCBhbmQgZWxlY3Ryb25pYyBmb3JtYXQgYW5kIGluIGFueSBtZWRpdW0sCmluY2x1ZGluZyBidXQgbm90IGxpbWl0ZWQgdG8gYXVkaW8gb3IgdmlkZW8uCgpZb3UgYWdyZWUgdGhhdCBEU1UgbWF5LCB3aXRob3V0IGNoYW5naW5nIHRoZSBjb250ZW50LCB0cmFuc2xhdGUgdGhlCnN1Ym1pc3Npb24gdG8gYW55IG1lZGl1bSBvciBmb3JtYXQgZm9yIHRoZSBwdXJwb3NlIG9mIHByZXNlcnZhdGlvbi4KCllvdSBhbHNvIGFncmVlIHRoYXQgRFNVIG1heSBrZWVwIG1vcmUgdGhhbiBvbmUgY29weSBvZiB0aGlzIHN1Ym1pc3Npb24gZm9yCnB1cnBvc2VzIG9mIHNlY3VyaXR5LCBiYWNrLXVwIGFuZCBwcmVzZXJ2YXRpb24uCgpZb3UgcmVwcmVzZW50IHRoYXQgdGhlIHN1Ym1pc3Npb24gaXMgeW91ciBvcmlnaW5hbCB3b3JrLCBhbmQgdGhhdCB5b3UgaGF2ZQp0aGUgcmlnaHQgdG8gZ3JhbnQgdGhlIHJpZ2h0cyBjb250YWluZWQgaW4gdGhpcyBsaWNlbnNlLiBZb3UgYWxzbyByZXByZXNlbnQKdGhhdCB5b3VyIHN1Ym1pc3Npb24gZG9lcyBub3QsIHRvIHRoZSBiZXN0IG9mIHlvdXIga25vd2xlZGdlLCBpbmZyaW5nZSB1cG9uCmFueW9uZSdzIGNvcHlyaWdodC4KCklmIHRoZSBzdWJtaXNzaW9uIGNvbnRhaW5zIG1hdGVyaWFsIGZvciB3aGljaCB5b3UgZG8gbm90IGhvbGQgY29weXJpZ2h0LAp5b3UgcmVwcmVzZW50IHRoYXQgeW91IGhhdmUgb2J0YWluZWQgdGhlIHVucmVzdHJpY3RlZCBwZXJtaXNzaW9uIG9mIHRoZQpjb3B5cmlnaHQgb3duZXIgdG8gZ3JhbnQgRFNVIHRoZSByaWdodHMgcmVxdWlyZWQgYnkgdGhpcyBsaWNlbnNlLCBhbmQgdGhhdApzdWNoIHRoaXJkLXBhcnR5IG93bmVkIG1hdGVyaWFsIGlzIGNsZWFybHkgaWRlbnRpZmllZCBhbmQgYWNrbm93bGVkZ2VkCndpdGhpbiB0aGUgdGV4dCBvciBjb250ZW50IG9mIHRoZSBzdWJtaXNzaW9uLgoKSUYgVEhFIFNVQk1JU1NJT04gSVMgQkFTRUQgVVBPTiBXT1JLIFRIQVQgSEFTIEJFRU4gU1BPTlNPUkVEIE9SIFNVUFBPUlRFRApCWSBBTiBBR0VOQ1kgT1IgT1JHQU5JWkFUSU9OIE9USEVSIFRIQU4gRFNVLCBZT1UgUkVQUkVTRU5UIFRIQVQgWU9VIEhBVkUKRlVMRklMTEVEIEFOWSBSSUdIVCBPRiBSRVZJRVcgT1IgT1RIRVIgT0JMSUdBVElPTlMgUkVRVUlSRUQgQlkgU1VDSApDT05UUkFDVCBPUiBBR1JFRU1FTlQuCgpEU1Ugd2lsbCBjbGVhcmx5IGlkZW50aWZ5IHlvdXIgbmFtZShzKSBhcyB0aGUgYXV0aG9yKHMpIG9yIG93bmVyKHMpIG9mIHRoZQpzdWJtaXNzaW9uLCBhbmQgd2lsbCBub3QgbWFrZSBhbnkgYWx0ZXJhdGlvbiwgb3RoZXIgdGhhbiBhcyBhbGxvd2VkIGJ5IHRoaXMKbGljZW5zZSwgdG8geW91ciBzdWJtaXNzaW9uLgo=Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102020-04-12T23:11:05Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
title Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
spellingShingle Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
BORGES, EDUARDO M.
angra-2 reactor
cladding
eccs
heat transfer
primary coolant circuits
reactor accident simulation
reactor cores
sbloca
steady-state conditions
two-phase flow
void fraction
title_short Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
title_full Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
title_fullStr Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
title_full_unstemmed Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
title_sort Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
author BORGES, EDUARDO M.
author_facet BORGES, EDUARDO M.
SABUNDJIAN, GAIANE
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author_role author
author2 SABUNDJIAN, GAIANE
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author2_role author
author
dc.contributor.author.fl_str_mv BORGES, EDUARDO M.
SABUNDJIAN, GAIANE
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.subject.por.fl_str_mv angra-2 reactor
cladding
eccs
heat transfer
primary coolant circuits
reactor accident simulation
reactor cores
sbloca
steady-state conditions
two-phase flow
void fraction
topic angra-2 reactor
cladding
eccs
heat transfer
primary coolant circuits
reactor accident simulation
reactor cores
sbloca
steady-state conditions
two-phase flow
void fraction
description The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 200cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core.
publishDate 2020
dc.date.evento.pt_BR.fl_str_mv October 21-25, 2019
dc.date.accessioned.fl_str_mv 2020-01-15T18:35:17Z
dc.date.available.fl_str_mv 2020-01-15T18:35:17Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
dc.type.driver.fl_str_mv info:eu-repo/semantics/conferenceObject
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status_str publishedVersion
dc.identifier.uri.fl_str_mv http://repositorio.ipen.br/handle/123456789/30728
dc.identifier.orcid.pt_BR.fl_str_mv 0000-0001-9544-4509
url http://repositorio.ipen.br/handle/123456789/30728
identifier_str_mv 0000-0001-9544-4509
dc.relation.authority.fl_str_mv 11597
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dc.relation.confidence.fl_str_mv 600
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dc.rights.driver.fl_str_mv info:eu-repo/semantics/openAccess
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv 5479-5490
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)
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instname_str Instituto de Pesquisas Energéticas e Nucleares (IPEN)
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institution IPEN
reponame_str Repositório Institucional do IPEN
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