Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core

Detalhes bibliográficos
Autor(a) principal: SILVA, A.T.
Data de Publicação: 2014
Outros Autores: ALMEIDA, C.T., UMBEHAUN, P.E., YAMAGUSHI, M., SILVA, J.E.R., LUCKI, G., INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 10th
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/13771
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spelling 2014-11-17T17:25:49Z2014-11-18T17:34:07Z2015-04-01T21:30:11Z2014-11-17T17:25:49Z2014-11-18T17:34:07Z2015-04-01T21:30:11ZApril 30 - May 3, 2006http://repositorio.ipen.br/handle/123456789/13771Made available in DSpace on 2014-11-17T17:25:49Z (GMT). No. of bitstreams: 0Made available in DSpace on 2014-11-18T17:34:07Z (GMT). No. of bitstreams: 1 15470.pdf: 465409 bytes, checksum: 532e2daaa870bd411dc9b4bf1d465414 (MD5)Made available in DSpace on 2015-04-01T21:30:11Z (GMT). No. of bitstreams: 1 15470.pdf: 465409 bytes, checksum: 532e2daaa870bd411dc9b4bf1d465414 (MD5)145-149iear-1 reactorreactor coresuraniummolybdenumdispersion nuclear fuelsmaterials testing reactorsreactor operationprogrammingNeutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor coreinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectISofia, BulgariaSILVA, A.T.ALMEIDA, C.T.UMBEHAUN, P.E.YAMAGUSHI, M.SILVA, J.E.R.LUCKI, G.INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 10thinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN154702006SILVA, A.T.UMBEHAUN, P.E.YAMAGUSHI, M.SILVA, J.E.R.10-08Proceedings108531237541338137443SILVA, A.T.:1085:21:SALMEIDA, C.T.:3123:-1:NUMBEHAUN, P.E.:754:21:NYAMAGUSHI, M.:1338:21:NSILVA, J.E.R.:137:21:NLUCKI, G.:443:21:NORIGINAL15470.pdfapplication/pdf465409http://repositorio.ipen.br/bitstream/123456789/13771/1/15470.pdf532e2daaa870bd411dc9b4bf1d465414MD51123456789/137712015-04-01 21:30:11.088oai:repositorio.ipen.br:123456789/13771Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102015-04-01T21:30:11Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
title Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
spellingShingle Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
SILVA, A.T.
iear-1 reactor
reactor cores
uranium
molybdenum
dispersion nuclear fuels
materials testing reactors
reactor operation
programming
title_short Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
title_full Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
title_fullStr Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
title_full_unstemmed Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
title_sort Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
author SILVA, A.T.
author_facet SILVA, A.T.
ALMEIDA, C.T.
UMBEHAUN, P.E.
YAMAGUSHI, M.
SILVA, J.E.R.
LUCKI, G.
INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 10th
author_role author
author2 ALMEIDA, C.T.
UMBEHAUN, P.E.
YAMAGUSHI, M.
SILVA, J.E.R.
LUCKI, G.
INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 10th
author2_role author
author
author
author
author
author
dc.contributor.author.fl_str_mv SILVA, A.T.
ALMEIDA, C.T.
UMBEHAUN, P.E.
YAMAGUSHI, M.
SILVA, J.E.R.
LUCKI, G.
INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 10th
dc.subject.por.fl_str_mv iear-1 reactor
reactor cores
uranium
molybdenum
dispersion nuclear fuels
materials testing reactors
reactor operation
programming
topic iear-1 reactor
reactor cores
uranium
molybdenum
dispersion nuclear fuels
materials testing reactors
reactor operation
programming
publishDate 2014
dc.date.evento.pt_BR.fl_str_mv April 30 - May 3, 2006
dc.date.accessioned.fl_str_mv 2014-11-17T17:25:49Z
2014-11-18T17:34:07Z
2015-04-01T21:30:11Z
dc.date.available.fl_str_mv 2014-11-17T17:25:49Z
2014-11-18T17:34:07Z
2015-04-01T21:30:11Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
dc.type.driver.fl_str_mv info:eu-repo/semantics/conferenceObject
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dc.rights.driver.fl_str_mv info:eu-repo/semantics/openAccess
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dc.format.none.fl_str_mv 145-149
dc.coverage.pt_BR.fl_str_mv I
dc.source.none.fl_str_mv reponame:Repositório Institucional do IPEN
instname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)
instacron:IPEN
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