Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation

Detalhes bibliográficos
Autor(a) principal: LIMA, LEONARDO S.
Data de Publicação: 2020
Outros Autores: MELO, CAIO, FARIA, DANILO P., BERRETA, JOSE, ABATI, AMANDA, GIOVEDI, CLAUDIA, INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/30813
Resumo: During operation of a Pressurized Water Reactor, the cladding of the fuel rod is subjected to various loads, such as: temperature, internal pressure, and external pressure which generate dimensional and geometric variations in the cladding tube. In the fuel rod, at the operating temperature, the internal pressure comes from the initial pre-pressurizing with Helium gas and the release of fission gases by the UO2 pellets during the irradiation. The external pressure is assumed to be the same as that of the coolant. In this paper, it was proposed the study of a mathematical model for computational simulation using the Finite Element Method to calculate and analyze the mechanical stresses acting on the internal and external surfaces of the fuel rod, adopting the normal operating condition, at 0 W of power. The boundary conditions, such as temperature and pressure profile, come from a modified version of a fuel performance code, considering as cladding material an iron-based alloy (austenitic stainless steel). The fuel rod was modeled and simulated using the Solidworks and ANSYS softwares, respectively. The values of the stresses acting on the cladding tube obtained by simulation were compared to the values obtained by analytical calculation. Then, it was checked the consistency of the adopted mathematical model, in order to ensure the reliability of the computational simulation as a tool to evaluate the stresses acting on the internal and external surfaces of the fuel rod under a PWR environment.
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spelling 2020-02-20T13:06:18Z2020-02-20T13:06:18ZOctober 21-25, 2019http://repositorio.ipen.br/handle/123456789/30813During operation of a Pressurized Water Reactor, the cladding of the fuel rod is subjected to various loads, such as: temperature, internal pressure, and external pressure which generate dimensional and geometric variations in the cladding tube. In the fuel rod, at the operating temperature, the internal pressure comes from the initial pre-pressurizing with Helium gas and the release of fission gases by the UO2 pellets during the irradiation. The external pressure is assumed to be the same as that of the coolant. In this paper, it was proposed the study of a mathematical model for computational simulation using the Finite Element Method to calculate and analyze the mechanical stresses acting on the internal and external surfaces of the fuel rod, adopting the normal operating condition, at 0 W of power. The boundary conditions, such as temperature and pressure profile, come from a modified version of a fuel performance code, considering as cladding material an iron-based alloy (austenitic stainless steel). The fuel rod was modeled and simulated using the Solidworks and ANSYS softwares, respectively. The values of the stresses acting on the cladding tube obtained by simulation were compared to the values obtained by analytical calculation. Then, it was checked the consistency of the adopted mathematical model, in order to ensure the reliability of the computational simulation as a tool to evaluate the stresses acting on the internal and external surfaces of the fuel rod under a PWR environment.Submitted by Celia Satomi Uehara (celia.u-topservice@ipen.br) on 2020-02-20T13:06:18Z No. of bitstreams: 1 26357.pdf: 1144585 bytes, checksum: d74efe6cfc6824664416a5e66520421b (MD5)Made available in DSpace on 2020-02-20T13:06:18Z (GMT). No. of bitstreams: 1 26357.pdf: 1144585 bytes, checksum: d74efe6cfc6824664416a5e66520421b (MD5)4950-4961Associa????o Brasileira de Energia Nucleara codesaustenitic steelsboundary conditionscladdingcomputerized simulationfinite element methodfuel rodsiron alloyspwr type reactorss codesstressesAnalysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulationinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de JaneiroSantos, SP31508940600600LIMA, LEONARDO S.MELO, CAIOFARIA, DANILO P.BERRETA, JOSEABATI, AMANDAGIOVEDI, CLAUDIAINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN263572019GIOVEDI, CLAUDIAABATI, AMANDA20-02Proceedings38703150GIOVEDI, CLAUDIA:3870:-1:NABATI, AMANDA:3150:-1:NORIGINAL26357.pdf26357.pdfapplication/pdf1144585http://repositorio.ipen.br/bitstream/123456789/30813/1/26357.pdfd74efe6cfc6824664416a5e66520421bMD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/30813/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/308132021-03-17 13:59:45.162oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102021-03-17T13:59:45Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
title Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
spellingShingle Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
LIMA, LEONARDO S.
a codes
austenitic steels
boundary conditions
cladding
computerized simulation
finite element method
fuel rods
iron alloys
pwr type reactors
s codes
stresses
title_short Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
title_full Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
title_fullStr Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
title_full_unstemmed Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
title_sort Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
author LIMA, LEONARDO S.
author_facet LIMA, LEONARDO S.
MELO, CAIO
FARIA, DANILO P.
BERRETA, JOSE
ABATI, AMANDA
GIOVEDI, CLAUDIA
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author_role author
author2 MELO, CAIO
FARIA, DANILO P.
BERRETA, JOSE
ABATI, AMANDA
GIOVEDI, CLAUDIA
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author2_role author
author
author
author
author
author
dc.contributor.author.fl_str_mv LIMA, LEONARDO S.
MELO, CAIO
FARIA, DANILO P.
BERRETA, JOSE
ABATI, AMANDA
GIOVEDI, CLAUDIA
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.subject.por.fl_str_mv a codes
austenitic steels
boundary conditions
cladding
computerized simulation
finite element method
fuel rods
iron alloys
pwr type reactors
s codes
stresses
topic a codes
austenitic steels
boundary conditions
cladding
computerized simulation
finite element method
fuel rods
iron alloys
pwr type reactors
s codes
stresses
description During operation of a Pressurized Water Reactor, the cladding of the fuel rod is subjected to various loads, such as: temperature, internal pressure, and external pressure which generate dimensional and geometric variations in the cladding tube. In the fuel rod, at the operating temperature, the internal pressure comes from the initial pre-pressurizing with Helium gas and the release of fission gases by the UO2 pellets during the irradiation. The external pressure is assumed to be the same as that of the coolant. In this paper, it was proposed the study of a mathematical model for computational simulation using the Finite Element Method to calculate and analyze the mechanical stresses acting on the internal and external surfaces of the fuel rod, adopting the normal operating condition, at 0 W of power. The boundary conditions, such as temperature and pressure profile, come from a modified version of a fuel performance code, considering as cladding material an iron-based alloy (austenitic stainless steel). The fuel rod was modeled and simulated using the Solidworks and ANSYS softwares, respectively. The values of the stresses acting on the cladding tube obtained by simulation were compared to the values obtained by analytical calculation. Then, it was checked the consistency of the adopted mathematical model, in order to ensure the reliability of the computational simulation as a tool to evaluate the stresses acting on the internal and external surfaces of the fuel rod under a PWR environment.
publishDate 2020
dc.date.evento.pt_BR.fl_str_mv October 21-25, 2019
dc.date.accessioned.fl_str_mv 2020-02-20T13:06:18Z
dc.date.available.fl_str_mv 2020-02-20T13:06:18Z
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/123456789/30813
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dc.format.none.fl_str_mv 4950-4961
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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
dc.source.none.fl_str_mv reponame:Repositório Institucional do IPEN
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