Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g
Autor(a) principal: | |
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Data de Publicação: | 2014 |
Outros Autores: | , |
Tipo de documento: | Artigo de conferência |
Título da fonte: | Repositório Institucional do IPEN |
Texto Completo: | http://repositorio.ipen.br/handle/123456789/16945 |
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2014-11-17T18:25:18Z2014-11-18T18:44:00Z2015-04-01T23:36:46Z2014-11-17T18:25:18Z2014-11-18T18:44:00Z2015-04-01T23:36:46ZAug. 11-16, 2002http://repositorio.ipen.br/handle/123456789/16945Made available in DSpace on 2014-11-17T18:25:18Z (GMT). No. of bitstreams: 0Made available in DSpace on 2014-11-18T18:44:00Z (GMT). No. of bitstreams: 1 08669.PDF: 195850 bytes, checksum: 47f93f57286ebb46887ed211190abfa8 (MD5)Made available in DSpace on 2015-04-01T23:36:46Z (GMT). No. of bitstreams: 1 08669.PDF: 195850 bytes, checksum: 47f93f57286ebb46887ed211190abfa8 (MD5)ABEN 2002Publicado tambem em: Rev. Bras. Pesqui. Desenvolv., v. 4, n. 2, p. 258-264, set. 2002reponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPENreactor accidentsloss of coolanteccscomputerized simulationr codesrisk assessmentreactor coressafety analysisprimary coolant circuitsangra-2 reactorreactor safetytransientsSimulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2ginfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINAC 2002; ENFIR,13; ENAN, 6IRio de Janeiro , RJRio de Janeiro, RJSABUNDJIAN, G.ANDRADE, D.A.INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; NATIONAL MEETING OF REACTOR PHYSICS AND THERMAL HYDRAULICS, 13th; NATIONAL MEETING ON NUCLEAR APPLICATIONS, 6thinfo:eu-repo/semantics/openAccess086692002SABUNDJIAN, G.ANDRADE, D.A.03-03Proceedings2021258SABUNDJIAN, G.:202:23:SANDRADE, D.A.:1258:23:NORIGINAL08669.PDFapplication/pdf195850http://repositorio.ipen.br/bitstream/123456789/16945/1/08669.PDF47f93f57286ebb46887ed211190abfa8MD51123456789/169452015-04-01 23:36:46.164oai:repositorio.ipen.br:123456789/16945Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102015-04-01T23:36:46Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false |
dc.title.pt_BR.fl_str_mv |
Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g |
title |
Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g |
spellingShingle |
Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g SABUNDJIAN, G. reactor accidents loss of coolant eccs computerized simulation r codes risk assessment reactor cores safety analysis primary coolant circuits angra-2 reactor reactor safety transients |
title_short |
Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g |
title_full |
Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g |
title_fullStr |
Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g |
title_full_unstemmed |
Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g |
title_sort |
Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g |
author |
SABUNDJIAN, G. |
author_facet |
SABUNDJIAN, G. ANDRADE, D.A. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; NATIONAL MEETING OF REACTOR PHYSICS AND THERMAL HYDRAULICS, 13th; NATIONAL MEETING ON NUCLEAR APPLICATIONS, 6th |
author_role |
author |
author2 |
ANDRADE, D.A. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; NATIONAL MEETING OF REACTOR PHYSICS AND THERMAL HYDRAULICS, 13th; NATIONAL MEETING ON NUCLEAR APPLICATIONS, 6th |
author2_role |
author author |
dc.contributor.author.fl_str_mv |
SABUNDJIAN, G. ANDRADE, D.A. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; NATIONAL MEETING OF REACTOR PHYSICS AND THERMAL HYDRAULICS, 13th; NATIONAL MEETING ON NUCLEAR APPLICATIONS, 6th |
dc.subject.por.fl_str_mv |
reactor accidents loss of coolant eccs computerized simulation r codes risk assessment reactor cores safety analysis primary coolant circuits angra-2 reactor reactor safety transients |
topic |
reactor accidents loss of coolant eccs computerized simulation r codes risk assessment reactor cores safety analysis primary coolant circuits angra-2 reactor reactor safety transients |
publishDate |
2014 |
dc.date.evento.pt_BR.fl_str_mv |
Aug. 11-16, 2002 |
dc.date.accessioned.fl_str_mv |
2014-11-17T18:25:18Z 2014-11-18T18:44:00Z 2015-04-01T23:36:46Z |
dc.date.available.fl_str_mv |
2014-11-17T18:25:18Z 2014-11-18T18:44:00Z 2015-04-01T23:36:46Z |
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/123456789/16945 |
url |
http://repositorio.ipen.br/handle/123456789/16945 |
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 |
ABEN 2002 |
publisher.none.fl_str_mv |
ABEN 2002 |
dc.source.pt_BR.fl_str_mv |
Publicado tambem em: Rev. Bras. Pesqui. Desenvolv., v. 4, n. 2, p. 258-264, set. 2002 |
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) |
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IPEN |
institution |
IPEN |
reponame_str |
Repositório Institucional do IPEN |
collection |
Repositório Institucional do IPEN |
bitstream.url.fl_str_mv |
http://repositorio.ipen.br/bitstream/123456789/16945/1/08669.PDF |
bitstream.checksum.fl_str_mv |
47f93f57286ebb46887ed211190abfa8 |
bitstream.checksumAlgorithm.fl_str_mv |
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 |
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1767254212078469120 |