Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2

Detalhes bibliográficos
Autor(a) principal: ANDRADE, D.A.
Data de Publicação: 2014
Outros Autores: SABUNDJIAN, G., UMBEHAUN, P.E., TORRES, W.M., INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; ENCONTRO NACIONAL DE FISICA E REATORES THERMAL HIDRAULICA, 14th
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/17637
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spelling 2014-11-17T18:35:26Z2014-11-18T18:28:10Z2015-04-02T03:08:39Z2014-11-17T18:35:26Z2014-11-18T18:28:10Z2015-04-02T03:08:39Zago. 28 - set. 2, 2005http://repositorio.ipen.br/handle/123456789/17637Made available in DSpace on 2014-11-17T18:35:26Z (GMT). No. of bitstreams: 0Made available in DSpace on 2014-11-18T18:28:10Z (GMT). No. of bitstreams: 1 10651.pdf: 273079 bytes, checksum: 0db1065ce9b2d20781ff3bcfa8eb7b98 (MD5)Made available in DSpace on 2015-04-02T03:08:39Z (GMT). No. of bitstreams: 1 10651.pdf: 273079 bytes, checksum: 0db1065ce9b2d20781ff3bcfa8eb7b98 (MD5)Sao Paulo: ABEN, 2005angra-2 reactorcomputerized simulationeccsexperimental dataloss of coolantprimary coolant circuitsr codesreactor corestemperature dependencethermal hydraulicstime dependencetransientsSimulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2info:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINAC,2005; ENFIR,14ISantos, SPANDRADE, D.A.SABUNDJIAN, G.UMBEHAUN, P.E.TORRES, W.M.INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; ENCONTRO NACIONAL DE FISICA E REATORES THERMAL HIDRAULICA, 14thinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN106512005ANDRADE, D.A.SABUNDJIAN, G.UMBEHAUN, P.E.TORRES, W.M.05-10Anais1258202754188ANDRADE, D.A.:1258:21:SSABUNDJIAN, G.:202:21:NUMBEHAUN, P.E.:754:21:NTORRES, W.M.:188:21:NORIGINAL10651.pdfapplication/pdf273079http://repositorio.ipen.br/bitstream/123456789/17637/1/10651.pdf0db1065ce9b2d20781ff3bcfa8eb7b98MD51123456789/176372015-04-02 03:08:39.103oai:repositorio.ipen.br:123456789/17637Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102015-04-02T03:08:39Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
title Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
spellingShingle Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
ANDRADE, D.A.
angra-2 reactor
computerized simulation
eccs
experimental data
loss of coolant
primary coolant circuits
r codes
reactor cores
temperature dependence
thermal hydraulics
time dependence
transients
title_short Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
title_full Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
title_fullStr Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
title_full_unstemmed Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
title_sort Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
author ANDRADE, D.A.
author_facet ANDRADE, D.A.
SABUNDJIAN, G.
UMBEHAUN, P.E.
TORRES, W.M.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; ENCONTRO NACIONAL DE FISICA E REATORES THERMAL HIDRAULICA, 14th
author_role author
author2 SABUNDJIAN, G.
UMBEHAUN, P.E.
TORRES, W.M.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; ENCONTRO NACIONAL DE FISICA E REATORES THERMAL HIDRAULICA, 14th
author2_role author
author
author
author
dc.contributor.author.fl_str_mv ANDRADE, D.A.
SABUNDJIAN, G.
UMBEHAUN, P.E.
TORRES, W.M.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; ENCONTRO NACIONAL DE FISICA E REATORES THERMAL HIDRAULICA, 14th
dc.subject.por.fl_str_mv angra-2 reactor
computerized simulation
eccs
experimental data
loss of coolant
primary coolant circuits
r codes
reactor cores
temperature dependence
thermal hydraulics
time dependence
transients
topic angra-2 reactor
computerized simulation
eccs
experimental data
loss of coolant
primary coolant circuits
r codes
reactor cores
temperature dependence
thermal hydraulics
time dependence
transients
publishDate 2014
dc.date.evento.pt_BR.fl_str_mv ago. 28 - set. 2, 2005
dc.date.accessioned.fl_str_mv 2014-11-17T18:35:26Z
2014-11-18T18:28:10Z
2015-04-02T03:08:39Z
dc.date.available.fl_str_mv 2014-11-17T18:35:26Z
2014-11-18T18:28:10Z
2015-04-02T03:08:39Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
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dc.publisher.none.fl_str_mv Sao Paulo: ABEN, 2005
publisher.none.fl_str_mv Sao Paulo: ABEN, 2005
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