Experimental investigation of critical velocity in fuel element for the RMB reactor
Autor(a) principal: | |
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Data de Publicação: | 2019 |
Outros Autores: | , |
Tipo de documento: | Artigo de conferência |
Título da fonte: | Repositório Institucional do IPEN |
Texto Completo: | http://repositorio.ipen.br/handle/123456789/29743 |
Resumo: | The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminum-coated 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 inside the fuel element assembly to form channel gaps between them of only a few millimeters wide through which the coolant flows. 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 work an experimental loop capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels was 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 had 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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2019-03-01T11:51:29Z2019-03-01T11:51:29ZNovember 25-28, 2018http://repositorio.ipen.br/handle/123456789/29743aguardandoThe fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminum-coated 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 inside the fuel element assembly to form channel gaps between them of only a few millimeters wide through which the coolant flows. 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 work an experimental loop capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels was 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 had 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 2019-03-01T11:51:29Z No. of bitstreams: 1 25523.pdf: 1599074 bytes, checksum: 59efe587f3ea155fbdd5e5daf628d4d9 (MD5)Made available in DSpace on 2019-03-01T11:51:29Z (GMT). No. of bitstreams: 1 25523.pdf: 1599074 bytes, checksum: 59efe587f3ea155fbdd5e5daf628d4d9 (MD5)Conselho Nacional de Desenvolvimento Cient??fico e Tecnol??gico (CNPq)CNPq: 481193/2012-0Associa????o Brasileira de Engenharia e Ci??ncias Mec??nicascritical velocitydeformationexperimental datafluid flowfuel assembliesfuel platesmtr reactorrmb reactorreactor coresnuclear fuelsfuel elementsExperimental investigation of critical velocity in fuel element for the RMB reactorinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectENCITIRio de Janeiro??guas de Lind??ia, SPCASTRO, ALFREDO J.A. deANDRADE, DELVONEI A. deBRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17thinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN255232018CASTRO, ALFREDO J.A. deANDRADE, DELVONEI A. de19-03Proceedings12551258CASTRO, ALFREDO J.A. DE:1255:420:SANDRADE, DELVONEI A. DE:1258:420:NORIGINAL25523.pdf25523.pdfapplication/pdf1599074http://repositorio.ipen.br/bitstream/123456789/29743/1/25523.pdf59efe587f3ea155fbdd5e5daf628d4d9MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/29743/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/297432020-02-14 12:26:40.544oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102020-02-14T12:26:40Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false |
dc.title.pt_BR.fl_str_mv |
Experimental investigation of critical velocity in fuel element for the RMB reactor |
title |
Experimental investigation of critical velocity in fuel element for the RMB reactor |
spellingShingle |
Experimental investigation of critical velocity in fuel element for the RMB reactor CASTRO, ALFREDO J.A. de critical velocity deformation experimental data fluid flow fuel assemblies fuel plates mtr reactor rmb reactor reactor cores nuclear fuels fuel elements |
title_short |
Experimental investigation of critical velocity in fuel element for the RMB reactor |
title_full |
Experimental investigation of critical velocity in fuel element for the RMB reactor |
title_fullStr |
Experimental investigation of critical velocity in fuel element for the RMB reactor |
title_full_unstemmed |
Experimental investigation of critical velocity in fuel element for the RMB reactor |
title_sort |
Experimental investigation of critical velocity in fuel element for the RMB reactor |
author |
CASTRO, ALFREDO J.A. de |
author_facet |
CASTRO, ALFREDO J.A. de ANDRADE, DELVONEI A. de BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th |
author_role |
author |
author2 |
ANDRADE, DELVONEI A. de BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th |
author2_role |
author author |
dc.contributor.author.fl_str_mv |
CASTRO, ALFREDO J.A. de ANDRADE, DELVONEI A. de BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th |
dc.subject.por.fl_str_mv |
critical velocity deformation experimental data fluid flow fuel assemblies fuel plates mtr reactor rmb reactor reactor cores nuclear fuels fuel elements |
topic |
critical velocity deformation experimental data fluid flow fuel assemblies fuel plates mtr reactor rmb reactor reactor cores nuclear fuels fuel elements |
description |
The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminum-coated 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 inside the fuel element assembly to form channel gaps between them of only a few millimeters wide through which the coolant flows. 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 work an experimental loop capable of high volume flows and a test section that simulates a plate-like fuel element with three cooling channels was 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 had 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 |
2019 |
dc.date.evento.pt_BR.fl_str_mv |
November 25-28, 2018 |
dc.date.accessioned.fl_str_mv |
2019-03-01T11:51:29Z |
dc.date.available.fl_str_mv |
2019-03-01T11:51:29Z |
dc.type.status.fl_str_mv |
info:eu-repo/semantics/publishedVersion |
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info:eu-repo/semantics/conferenceObject |
format |
conferenceObject |
status_str |
publishedVersion |
dc.identifier.uri.fl_str_mv |
http://repositorio.ipen.br/handle/123456789/29743 |
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aguardando |
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aguardando |
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info:eu-repo/semantics/openAccess |
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openAccess |
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I |
dc.publisher.none.fl_str_mv |
Associa????o Brasileira de Engenharia e Ci??ncias Mec??nicas |
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Associa????o Brasileira de Engenharia e Ci??ncias Mec??nicas |
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