Neutronic and thermal-hydraulics calculations of U-Mo dispersion fuel for utilization in the IEA-R1 reactor core
Autor(a) principal: | |
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Data de Publicação: | 2014 |
Outros Autores: | , , , , , |
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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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 |
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info:eu-repo/semantics/conferenceObject |
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conferenceObject |
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publishedVersion |
dc.identifier.uri.fl_str_mv |
http://repositorio.ipen.br/handle/123456789/13771 |
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http://repositorio.ipen.br/handle/123456789/13771 |
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info:eu-repo/semantics/openAccess |
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openAccess |
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145-149 |
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I |
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