RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop
Autor(a) principal: | |
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Data de Publicação: | 2020 |
Outros Autores: | , , , |
Tipo de documento: | Artigo de conferência |
Título da fonte: | Repositório Institucional do IPEN |
Texto Completo: | http://repositorio.ipen.br/handle/123456789/30727 |
Resumo: | The aim of this paper was to simulate and evaluate the basic design accident of 80 cm?? small break loss of coolant accident (SBLOCA) in the cold leg of the primary loop of the Angra2 nuclear power plant. In this simulation, it was verified that the actuation logics of the Angra2 Reactor Protection System (RPS) and the Emergency Core Cooling System (ECCS) used in this simulation worked correctly, maintaining core integrity with acceptable temperatures throughout the event. The results obtained were satisfactory when compared with those presented by the Angra2 Final Safety Analysis Report (FSAR/A2). |
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2020-01-15T18:32:25Z2020-01-15T18:32:25ZOctober 21-25, 2019http://repositorio.ipen.br/handle/123456789/307270000-0001-9544-4509The aim of this paper was to simulate and evaluate the basic design accident of 80 cm?? small break loss of coolant accident (SBLOCA) in the cold leg of the primary loop of the Angra2 nuclear power plant. In this simulation, it was verified that the actuation logics of the Angra2 Reactor Protection System (RPS) and the Emergency Core Cooling System (ECCS) used in this simulation worked correctly, maintaining core integrity with acceptable temperatures throughout the event. The results obtained were satisfactory when compared with those presented by the Angra2 Final Safety Analysis Report (FSAR/A2).Submitted by Celia Satomi Uehara (celia.u-topservice@ipen.br) on 2020-01-15T18:32:25Z No. of bitstreams: 1 26380.pdf: 1307455 bytes, checksum: d67c325d08e0c3cb9d31a12eb0c10408 (MD5)Made available in DSpace on 2020-01-15T18:32:25Z (GMT). No. of bitstreams: 1 26380.pdf: 1307455 bytes, checksum: d67c325d08e0c3cb9d31a12eb0c10408 (MD5)5469-5478Associa????o Brasileira de Energia Nuclearactuatorsangra-2 reactorboundary conditionsprimary coolant circuitsr codesreactor accident simulationreactor cooling systemsreactor coresreactor protection systemssafety analysissblocasteady-state conditionsvoid fractionRELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loopinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de JaneiroSantos, SP11597202600600BORGES, EDUARDO M.SABUNDJIAN, GAIANEBRAZ FILHO, FRANCISCO A.GUIMAR??ES, LAMARTINE N.F.INTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN263802019SABUNDJIAN, GAIANEBORGES, EDUARDO M.20-01Proceedings20211597SABUNDJIAN, GAIANE:202:420:NBORGES, EDUARDO M.:11597:-1:SORIGINAL26380.pdf26380.pdfapplication/pdf1307455http://repositorio.ipen.br/bitstream/123456789/30727/1/26380.pdfd67c325d08e0c3cb9d31a12eb0c10408MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/30727/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/307272020-04-12 23:06:36.213oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102020-04-12T23:06:36Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false |
dc.title.pt_BR.fl_str_mv |
RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop |
title |
RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop |
spellingShingle |
RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop BORGES, EDUARDO M. actuators angra-2 reactor boundary conditions primary coolant circuits r codes reactor accident simulation reactor cooling systems reactor cores reactor protection systems safety analysis sbloca steady-state conditions void fraction |
title_short |
RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop |
title_full |
RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop |
title_fullStr |
RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop |
title_full_unstemmed |
RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop |
title_sort |
RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop |
author |
BORGES, EDUARDO M. |
author_facet |
BORGES, EDUARDO M. SABUNDJIAN, GAIANE BRAZ FILHO, FRANCISCO A. GUIMAR??ES, LAMARTINE N.F. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author_role |
author |
author2 |
SABUNDJIAN, GAIANE BRAZ FILHO, FRANCISCO A. GUIMAR??ES, LAMARTINE N.F. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author2_role |
author author author author |
dc.contributor.author.fl_str_mv |
BORGES, EDUARDO M. SABUNDJIAN, GAIANE BRAZ FILHO, FRANCISCO A. GUIMAR??ES, LAMARTINE N.F. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
dc.subject.por.fl_str_mv |
actuators angra-2 reactor boundary conditions primary coolant circuits r codes reactor accident simulation reactor cooling systems reactor cores reactor protection systems safety analysis sbloca steady-state conditions void fraction |
topic |
actuators angra-2 reactor boundary conditions primary coolant circuits r codes reactor accident simulation reactor cooling systems reactor cores reactor protection systems safety analysis sbloca steady-state conditions void fraction |
description |
The aim of this paper was to simulate and evaluate the basic design accident of 80 cm?? small break loss of coolant accident (SBLOCA) in the cold leg of the primary loop of the Angra2 nuclear power plant. In this simulation, it was verified that the actuation logics of the Angra2 Reactor Protection System (RPS) and the Emergency Core Cooling System (ECCS) used in this simulation worked correctly, maintaining core integrity with acceptable temperatures throughout the event. The results obtained were satisfactory when compared with those presented by the Angra2 Final Safety Analysis Report (FSAR/A2). |
publishDate |
2020 |
dc.date.evento.pt_BR.fl_str_mv |
October 21-25, 2019 |
dc.date.accessioned.fl_str_mv |
2020-01-15T18:32:25Z |
dc.date.available.fl_str_mv |
2020-01-15T18:32:25Z |
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/123456789/30727 |
dc.identifier.orcid.pt_BR.fl_str_mv |
0000-0001-9544-4509 |
url |
http://repositorio.ipen.br/handle/123456789/30727 |
identifier_str_mv |
0000-0001-9544-4509 |
dc.relation.authority.fl_str_mv |
11597 202 |
dc.relation.confidence.fl_str_mv |
600 600 |
dc.rights.driver.fl_str_mv |
info:eu-repo/semantics/openAccess |
eu_rights_str_mv |
openAccess |
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5469-5478 |
dc.coverage.pt_BR.fl_str_mv |
I |
dc.publisher.none.fl_str_mv |
Associa????o Brasileira de Energia Nuclear |
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Associa????o Brasileira de Energia Nuclear |
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reponame:Repositório Institucional do IPEN instname:Instituto de Pesquisas Energéticas e Nucleares (IPEN) instacron:IPEN |
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