RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop

Detalhes bibliográficos
Autor(a) principal: BORGES, EDUARDO M.
Data de Publicação: 2020
Outros Autores: SABUNDJIAN, GAIANE, BRAZ FILHO, FRANCISCO A., GUIMAR??ES, LAMARTINE N.F., INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/30727
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).
id IPEN_34800f86ea8649f67824b5484b84b86c
oai_identifier_str oai:repositorio.ipen.br:123456789/30727
network_acronym_str IPEN
network_name_str Repositório Institucional do IPEN
repository_id_str 4510
spelling 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
dc.format.none.fl_str_mv 5469-5478
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/123456789/30727/1/26380.pdf
http://repositorio.ipen.br/bitstream/123456789/30727/2/license.txt
bitstream.checksum.fl_str_mv d67c325d08e0c3cb9d31a12eb0c10408
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_ 1767254250671308800

Registros relacionados