Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor

Detalhes bibliográficos
Autor(a) principal: DOMINGOS, DOUGLAS B.
Data de Publicação: 2014
Outros Autores: TEIXEIRA e SILVA, ANTONIO, UMBEHAUN, PEDRO E., SILVA, JOSE E.R. da, CONTI, THADEU das N., YAMAGUCHI, MITSUO, INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/16611
id IPEN_e8f63108ddea114820fe5d3ba5a7ab16
oai_identifier_str oai:repositorio.ipen.br:123456789/16611
network_acronym_str IPEN
network_name_str Repositório Institucional do IPEN
repository_id_str 4510
spelling 2014-11-17T18:19:56Z2014-11-18T18:27:41Z2015-04-02T03:22:04Z2014-11-17T18:19:56Z2014-11-18T18:27:41Z2015-04-02T03:22:04ZSeptember 27 - October 2, 2009http://repositorio.ipen.br/handle/123456789/16611Made available in DSpace on 2014-11-17T18:19:56Z (GMT). No. of bitstreams: 0Made available in DSpace on 2014-11-18T18:27:41Z (GMT). No. of bitstreams: 1 15265.pdf: 579668 bytes, checksum: 5085767b31f0875f3bfef17880e06fae (MD5)Made available in DSpace on 2015-04-02T03:22:04Z (GMT). No. of bitstreams: 1 15265.pdf: 579668 bytes, checksum: 5085767b31f0875f3bfef17880e06fae (MD5)Sao Paulo: ABEN, 2009c codesdispersion nuclear fuelsf codesflow rateiear-1 reactorirradiation devicesl codesloss of coolantreactor corest codesthermal hydraulicsuranium oxides u3o8Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactorinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINAC; ENAN; ENFIR; ENINIRio de Janeiro, RJDOMINGOS, DOUGLAS B.TEIXEIRA e SILVA, ANTONIOUMBEHAUN, PEDRO E.SILVA, JOSE E.R. daCONTI, THADEU das N.YAMAGUCHI, MITSUOINTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1stinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN152652009TEIXEIRA e SILVA, ANTONIOUMBEHAUN, PEDRO E.SILVA, JOSE E.R. daCONTI, THADEU das N.YAMAGUCHI, MITSUO09-10Proceedings748210857541372841338DOMINGOS, DOUGLAS B.:7482:420:STEIXEIRA e SILVA, ANTONIO:1085:420:NUMBEHAUN, PEDRO E.:754:420:NSILVA, JOSE E.R. DA:137:420:NCONTI, THADEU DAS N.:284:420:NYAMAGUCHI, MITSUO:1338:420:NORIGINAL15265.pdfapplication/pdf579668http://repositorio.ipen.br/bitstream/123456789/16611/1/15265.pdf5085767b31f0875f3bfef17880e06faeMD51123456789/166112016-06-07 11:35:07.217oai:repositorio.ipen.br:123456789/16611Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102016-06-07T11:35:07Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor
title Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor
spellingShingle Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor
DOMINGOS, DOUGLAS B.
c codes
dispersion nuclear fuels
f codes
flow rate
iear-1 reactor
irradiation devices
l codes
loss of coolant
reactor cores
t codes
thermal hydraulics
uranium oxides u3o8
title_short Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor
title_full Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor
title_fullStr Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor
title_full_unstemmed Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor
title_sort Neutronic, thermal-hydraulic and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research reactor
author DOMINGOS, DOUGLAS B.
author_facet DOMINGOS, DOUGLAS B.
TEIXEIRA e SILVA, ANTONIO
UMBEHAUN, PEDRO E.
SILVA, JOSE E.R. da
CONTI, THADEU das N.
YAMAGUCHI, MITSUO
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st
author_role author
author2 TEIXEIRA e SILVA, ANTONIO
UMBEHAUN, PEDRO E.
SILVA, JOSE E.R. da
CONTI, THADEU das N.
YAMAGUCHI, MITSUO
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st
author2_role author
author
author
author
author
author
dc.contributor.author.fl_str_mv DOMINGOS, DOUGLAS B.
TEIXEIRA e SILVA, ANTONIO
UMBEHAUN, PEDRO E.
SILVA, JOSE E.R. da
CONTI, THADEU das N.
YAMAGUCHI, MITSUO
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st
dc.subject.por.fl_str_mv c codes
dispersion nuclear fuels
f codes
flow rate
iear-1 reactor
irradiation devices
l codes
loss of coolant
reactor cores
t codes
thermal hydraulics
uranium oxides u3o8
topic c codes
dispersion nuclear fuels
f codes
flow rate
iear-1 reactor
irradiation devices
l codes
loss of coolant
reactor cores
t codes
thermal hydraulics
uranium oxides u3o8
publishDate 2014
dc.date.evento.pt_BR.fl_str_mv September 27 - October 2, 2009
dc.date.accessioned.fl_str_mv 2014-11-17T18:19:56Z
2014-11-18T18:27:41Z
2015-04-02T03:22:04Z
dc.date.available.fl_str_mv 2014-11-17T18:19:56Z
2014-11-18T18:27:41Z
2015-04-02T03:22:04Z
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/123456789/16611
url http://repositorio.ipen.br/handle/123456789/16611
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, 2009
publisher.none.fl_str_mv Sao Paulo: ABEN, 2009
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/123456789/16611/1/15265.pdf
bitstream.checksum.fl_str_mv 5085767b31f0875f3bfef17880e06fae
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
_version_ 1767254223245803520

Registros relacionados