Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5

Detalhes bibliográficos
Autor(a) principal: ROCHA, R.T.V.
Data de Publicação: 2014
Outros Autores: ANDRADE, D.A., SABUNDJIAN, G., BELCHIOR JUNIOR, A., 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/123456789/17627
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spelling 2014-11-17T18:35:16Z2014-11-18T18:28:28Z2015-04-02T03:18:55Z2014-11-17T18:35:16Z2014-11-18T18:28:28Z2015-04-02T03:18:55Zago. 28 - set. 2, 2005http://repositorio.ipen.br/handle/123456789/17627Made available in DSpace on 2014-11-17T18:35:16Z (GMT). No. of bitstreams: 0Made available in DSpace on 2014-11-18T18:28:28Z (GMT). No. of bitstreams: 1 10697.pdf: 230713 bytes, checksum: d75ef9e218017a1d8c8d799058a8a08f (MD5)Made available in DSpace on 2015-04-02T03:18:55Z (GMT). No. of bitstreams: 1 10697.pdf: 230713 bytes, checksum: d75ef9e218017a1d8c8d799058a8a08f (MD5)Sao Paulo: ABEN, 2005boundary conditionsc codescomputerized simulationfuel elementsiear-1 reactorp codespower distributionr codesreactor coresreactor shutdowntemperature measurementtime dependencevalidationModelagem do nucleo do reator IEA-R1 com o codigo RELAP5info:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINAC,2005; ENFIR,14ISantos, SPROCHA, R.T.V.ANDRADE, D.A.SABUNDJIAN, G.BELCHIOR JUNIOR, A.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:IPEN106972005ANDRADE, D.A.SABUNDJIAN, G.BELCHIOR JUNIOR, A.UMBEHAUN, P.E.TORRES, W.M.05-10Anais636812582026367754188ROCHA, R.T.V.:6368:-1:SANDRADE, D.A.:1258:21:NSABUNDJIAN, G.:202:21:NBELCHIOR JUNIOR, A.:6367:-1:NUMBEHAUN, P.E.:754:21:NTORRES, W.M.:188:21:NORIGINAL10697.pdfapplication/pdf230713http://repositorio.ipen.br/bitstream/123456789/17627/1/10697.pdfd75ef9e218017a1d8c8d799058a8a08fMD51123456789/176272015-04-02 03:18:55.458oai:repositorio.ipen.br:123456789/17627Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102015-04-02T03:18:55Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
title Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
spellingShingle Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
ROCHA, R.T.V.
boundary conditions
c codes
computerized simulation
fuel elements
iear-1 reactor
p codes
power distribution
r codes
reactor cores
reactor shutdown
temperature measurement
time dependence
validation
title_short Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
title_full Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
title_fullStr Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
title_full_unstemmed Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
title_sort Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
author ROCHA, R.T.V.
author_facet ROCHA, R.T.V.
ANDRADE, D.A.
SABUNDJIAN, G.
BELCHIOR JUNIOR, A.
UMBEHAUN, P.E.
TORRES, W.M.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; ENCONTRO NACIONAL DE FISICA E REATORES THERMAL HIDRAULICA, 14th
author_role author
author2 ANDRADE, D.A.
SABUNDJIAN, G.
BELCHIOR JUNIOR, A.
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
author
author
dc.contributor.author.fl_str_mv ROCHA, R.T.V.
ANDRADE, D.A.
SABUNDJIAN, G.
BELCHIOR JUNIOR, A.
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 boundary conditions
c codes
computerized simulation
fuel elements
iear-1 reactor
p codes
power distribution
r codes
reactor cores
reactor shutdown
temperature measurement
time dependence
validation
topic boundary conditions
c codes
computerized simulation
fuel elements
iear-1 reactor
p codes
power distribution
r codes
reactor cores
reactor shutdown
temperature measurement
time dependence
validation
publishDate 2014
dc.date.evento.pt_BR.fl_str_mv ago. 28 - set. 2, 2005
dc.date.accessioned.fl_str_mv 2014-11-17T18:35:16Z
2014-11-18T18:28:28Z
2015-04-02T03:18:55Z
dc.date.available.fl_str_mv 2014-11-17T18:35:16Z
2014-11-18T18:28:28Z
2015-04-02T03:18:55Z
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/123456789/17627
url http://repositorio.ipen.br/handle/123456789/17627
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 Sao Paulo: ABEN, 2005
publisher.none.fl_str_mv Sao Paulo: ABEN, 2005
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/123456789/17627/1/10697.pdf
bitstream.checksum.fl_str_mv d75ef9e218017a1d8c8d799058a8a08f
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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