Experimental investigation of critical velocity in fuel element for the RMB reactor

Detalhes bibliográficos
Autor(a) principal: CASTRO, ALFREDO J.A. de
Data de Publicação: 2019
Outros Autores: ANDRADE, DELVONEI A. de, BRAZILIAN CONGRESS OF THERMAL SCIENCES AND ENGINEERING, 17th
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.
id IPEN_16cfbf7a1ea2dbf92d670202b516aec5
oai_identifier_str oai:repositorio.ipen.br:123456789/29743
network_acronym_str IPEN
network_name_str Repositório Institucional do IPEN
repository_id_str 4510
spelling 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
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/123456789/29743
dc.identifier.orcid.pt_BR.fl_str_mv aguardando
url http://repositorio.ipen.br/handle/123456789/29743
identifier_str_mv aguardando
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 Engenharia e Ci??ncias Mec??nicas
publisher.none.fl_str_mv Associa????o Brasileira de Engenharia e Ci??ncias Mec??nicas
dc.source.none.fl_str_mv reponame:Repositório Institucional do IPEN
instname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)
instacron:IPEN
instname_str Instituto de Pesquisas Energéticas e Nucleares (IPEN)
instacron_str IPEN
institution IPEN
reponame_str Repositório Institucional do IPEN
collection Repositório Institucional do IPEN
bitstream.url.fl_str_mv http://repositorio.ipen.br/bitstream/123456789/29743/1/25523.pdf
http://repositorio.ipen.br/bitstream/123456789/29743/2/license.txt
bitstream.checksum.fl_str_mv 59efe587f3ea155fbdd5e5daf628d4d9
8a4605be74aa9ea9d79846c1fba20a33
bitstream.checksumAlgorithm.fl_str_mv MD5
MD5
repository.name.fl_str_mv Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)
repository.mail.fl_str_mv bibl@ipen.br
_version_ 1767254247079936000