Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly
Autor(a) principal: | |
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Data de Publicação: | 2018 |
Outros Autores: | , , |
Tipo de documento: | Artigo de conferência |
Título da fonte: | Repositório Institucional do IPEN |
Texto Completo: | http://repositorio.ipen.br/handle/123456789/28204 |
Resumo: | The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminumcoated fuel plates containing the core of uranium silica (U3Si2) dispersed in an aluminum matrix. These plates have a thickness of the order of millimeters and are much longer in relation to their thickness. They are arranged in parallel in the assembly of the fuel element to form channels between them a few millimeters in thickness, through which there is a flow of the coolant. This configuration, combined with the need for a flow at high flow rates to ensure the cooling of the fuel element in operation, may create problems of mechanical failure of fuel plate due to the vibration induced by the flow in the channels. In the case of critical velocity excessive permanent deflections of the plates can cause blockage of the flow channel in the reactor core and lead to overheating in the plates. For this study an experimental bench capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels were developed. The dimensions of the test section were based on the dimensions of the Fuel Element of the Brazilian Multipurpose Reactor (RMB), whose project is being coordinated by the National Commission of Nuclear Energy (CNEN). The experiments performed attained the objective of reaching Miller's critical velocity condition. The critical velocity was reached with 14.5 m/s leading to the consequent plastic deformation of the flow channel plates. |
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2018-01-03T10:40:58Z2018-01-03T10:40:58ZOctober 22-27, 2017http://repositorio.ipen.br/handle/123456789/28204The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminumcoated fuel plates containing the core of uranium silica (U3Si2) dispersed in an aluminum matrix. These plates have a thickness of the order of millimeters and are much longer in relation to their thickness. They are arranged in parallel in the assembly of the fuel element to form channels between them a few millimeters in thickness, through which there is a flow of the coolant. This configuration, combined with the need for a flow at high flow rates to ensure the cooling of the fuel element in operation, may create problems of mechanical failure of fuel plate due to the vibration induced by the flow in the channels. In the case of critical velocity excessive permanent deflections of the plates can cause blockage of the flow channel in the reactor core and lead to overheating in the plates. For this study an experimental bench capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels were developed. The dimensions of the test section were based on the dimensions of the Fuel Element of the Brazilian Multipurpose Reactor (RMB), whose project is being coordinated by the National Commission of Nuclear Energy (CNEN). The experiments performed attained the objective of reaching Miller's critical velocity condition. The critical velocity was reached with 14.5 m/s leading to the consequent plastic deformation of the flow channel plates.Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2018-01-03T10:40:58Z No. of bitstreams: 1 24029.pdf: 1207059 bytes, checksum: 80dd9ed6c01bebf3df3b1143164a9d5c (MD5)Made available in DSpace on 2018-01-03T10:40:58Z (GMT). No. of bitstreams: 1 24029.pdf: 1207059 bytes, checksum: 80dd9ed6c01bebf3df3b1143164a9d5c (MD5)Associa????o Brasileira de Energia Nuclearcritical velocitydeformationexperimental datafluid flowfuel assembliesfuel platesmtr reactornuclear fuelsreactor coresExperimental investigation of critical velocity in a parallel plate research reactor fuel assemblyinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de Janeiro, RJBelo Horizonte, MGCASTRO, ALFREDO J.A.SCURO, NIKOLAS L.ANDRADE, DELVONEI A.INTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN240292017CASTRO, ALFREDO J.A.SCURO, NIKOLAS L.ANDRADE, DELVONEI A.18-01Proceedings1255145521258CASTRO, ALFREDO J.A.:1255:420:SSCURO, NIKOLAS L.:14552:-1:NANDRADE, DELVONEI A.:1258:420:NORIGINAL24029.pdf24029.pdfapplication/pdf1207059http://repositorio.ipen.br/bitstream/123456789/28204/1/24029.pdf80dd9ed6c01bebf3df3b1143164a9d5cMD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/28204/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/282042019-12-17 13:34:47.204oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102019-12-17T13:34:47Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false |
dc.title.pt_BR.fl_str_mv |
Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly |
title |
Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly |
spellingShingle |
Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly CASTRO, ALFREDO J.A. critical velocity deformation experimental data fluid flow fuel assemblies fuel plates mtr reactor nuclear fuels reactor cores |
title_short |
Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly |
title_full |
Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly |
title_fullStr |
Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly |
title_full_unstemmed |
Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly |
title_sort |
Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly |
author |
CASTRO, ALFREDO J.A. |
author_facet |
CASTRO, ALFREDO J.A. SCURO, NIKOLAS L. ANDRADE, DELVONEI A. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author_role |
author |
author2 |
SCURO, NIKOLAS L. ANDRADE, DELVONEI A. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author2_role |
author author author |
dc.contributor.author.fl_str_mv |
CASTRO, ALFREDO J.A. SCURO, NIKOLAS L. ANDRADE, DELVONEI A. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
dc.subject.por.fl_str_mv |
critical velocity deformation experimental data fluid flow fuel assemblies fuel plates mtr reactor nuclear fuels reactor cores |
topic |
critical velocity deformation experimental data fluid flow fuel assemblies fuel plates mtr reactor nuclear fuels reactor cores |
description |
The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminumcoated fuel plates containing the core of uranium silica (U3Si2) dispersed in an aluminum matrix. These plates have a thickness of the order of millimeters and are much longer in relation to their thickness. They are arranged in parallel in the assembly of the fuel element to form channels between them a few millimeters in thickness, through which there is a flow of the coolant. This configuration, combined with the need for a flow at high flow rates to ensure the cooling of the fuel element in operation, may create problems of mechanical failure of fuel plate due to the vibration induced by the flow in the channels. In the case of critical velocity excessive permanent deflections of the plates can cause blockage of the flow channel in the reactor core and lead to overheating in the plates. For this study an experimental bench capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels were developed. The dimensions of the test section were based on the dimensions of the Fuel Element of the Brazilian Multipurpose Reactor (RMB), whose project is being coordinated by the National Commission of Nuclear Energy (CNEN). The experiments performed attained the objective of reaching Miller's critical velocity condition. The critical velocity was reached with 14.5 m/s leading to the consequent plastic deformation of the flow channel plates. |
publishDate |
2018 |
dc.date.evento.pt_BR.fl_str_mv |
October 22-27, 2017 |
dc.date.accessioned.fl_str_mv |
2018-01-03T10:40:58Z |
dc.date.available.fl_str_mv |
2018-01-03T10:40:58Z |
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/123456789/28204 |
url |
http://repositorio.ipen.br/handle/123456789/28204 |
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 |
Associa????o Brasileira de Energia Nuclear |
publisher.none.fl_str_mv |
Associa????o Brasileira de Energia Nuclear |
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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Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
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IPEN |
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IPEN |
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Repositório Institucional do IPEN |
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Repositório Institucional do IPEN |
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http://repositorio.ipen.br/bitstream/123456789/28204/1/24029.pdf http://repositorio.ipen.br/bitstream/123456789/28204/2/license.txt |
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Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
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bibl@ipen.br |
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