RELAP5 code simulation of the small break loss of coolant accident of 80 cm² in the cold leg of Angra2 primary loop
dc.contributor.author | BORGES, EDUARDO M. | pt_BR |
dc.contributor.author | SABUNDJIAN, GAIANE | pt_BR |
dc.contributor.author | BRAZ FILHO, FRANCISCO A. | pt_BR |
dc.contributor.author | GUIMARÃES, LAMARTINE N.F. | pt_BR |
dc.coverage | Internacional | pt_BR |
dc.creator.evento | INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE | pt_BR |
dc.date.accessioned | 2020-01-15T18:32:25Z | |
dc.date.available | 2020-01-15T18:32:25Z | |
dc.date.evento | October 21-25, 2019 | pt_BR |
dc.description.abstract | The aim of this paper was to simulate and evaluate the basic design accident of 80 cm² 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). | pt_BR |
dc.event.sigla | INAC | pt_BR |
dc.format.extent | 5469-5478 | pt_BR |
dc.identifier.citation | BORGES, EDUARDO M.; SABUNDJIAN, GAIANE; BRAZ FILHO, FRANCISCO A.; GUIMARÃES, LAMARTINE N.F. RELAP5 code simulation of the small break loss of coolant accident of 80 cm² in the cold leg of Angra2 primary loop. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5469-5478. Disponível em: http://repositorio.ipen.br/handle/123456789/30727. | |
dc.identifier.orcid | 0000-0001-9544-4509 | pt_BR |
dc.identifier.orcid | https://orcid.org/0000-0001-9544-4509 | |
dc.identifier.uri | http://repositorio.ipen.br/handle/123456789/30727 | |
dc.local | Rio de Janeiro | pt_BR |
dc.local.evento | Santos, SP | pt_BR |
dc.publisher | Associação Brasileira de Energia Nuclear | |
dc.rights | openAccess | pt_BR |
dc.subject | actuators | |
dc.subject | angra-2 reactor | |
dc.subject | boundary conditions | |
dc.subject | primary coolant circuits | |
dc.subject | r codes | |
dc.subject | reactor accident simulation | |
dc.subject | reactor cooling systems | |
dc.subject | reactor cores | |
dc.subject | reactor protection systems | |
dc.subject | safety analysis | |
dc.subject | sbloca | |
dc.subject | steady-state conditions | |
dc.subject | void fraction | |
dc.title | RELAP5 code simulation of the small break loss of coolant accident of 80 cm² in the cold leg of Angra2 primary loop | pt_BR |
dc.type | Texto completo de evento | pt_BR |
dspace.entity.type | Publication | |
ipen.autor | GAIANE SABUNDJIAN | |
ipen.autor | EDUARDO MADEIRA BORGES | |
ipen.codigoautor | 202 | |
ipen.codigoautor | 11597 | |
ipen.contributor.ipenauthor | GAIANE SABUNDJIAN | |
ipen.contributor.ipenauthor | EDUARDO MADEIRA BORGES | |
ipen.date.recebimento | 20-01 | |
ipen.event.datapadronizada | 2019 | pt_BR |
ipen.identifier.ipendoc | 26380 | pt_BR |
ipen.notas.internas | Proceedings | pt_BR |
ipen.type.genre | Artigo | |
relation.isAuthorOfPublication | 915b9343-9eaf-4b03-b709-85699f77b71c | |
relation.isAuthorOfPublication | 0874438b-9df3-431a-9017-cff45ec95482 | |
relation.isAuthorOfPublication.latestForDiscovery | 0874438b-9df3-431a-9017-cff45ec95482 | |
sigepi.autor.atividade | SABUNDJIAN, GAIANE:202:420:N | pt_BR |
sigepi.autor.atividade | BORGES, EDUARDO M.:11597:-1:S | pt_BR |