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

Detalhes bibliográficos
Autor(a) principal: SABUNDJIAN, G.
Data de Publicação: 2014
Outros Autores: ANDRADE, D.A., INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; NATIONAL MEETING OF REACTOR PHYSICS AND THERMAL HYDRAULICS, 13th; NATIONAL MEETING ON NUCLEAR APPLICATIONS, 6th
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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spelling 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
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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)
instacron_str IPEN
institution IPEN
reponame_str Repositório Institucional do IPEN
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