Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly

Detalhes bibliográficos
Autor(a) principal: CASTRO, ALFREDO J.A.
Data de Publicação: 2018
Outros Autores: SCURO, NIKOLAS L., ANDRADE, DELVONEI A., INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
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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spelling 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
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dc.identifier.uri.fl_str_mv http://repositorio.ipen.br/handle/123456789/28204
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dc.publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
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