The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code

Detalhes bibliográficos
Autor(a) principal: SANCHEZ, ANDREA
Data de Publicação: 2020
Outros Autores: CARLUCCIO, THIAGO, SABUNDJIAN, GAIANE, INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/30729
Resumo: The Purdue Advanced Reactor Core Simulator (PARCS) is a computer code that solves the time-dependent two-group neutron diffusion equation in three-dimensional Cartesian geometry using nodal methods to obtain the transient neutron flux distribution. The code is used in the analysis of reactivity-initiated accidents in light-water reactors where spatial effects may be important. It may be run in the stand-alone mode or coupled to other NRC thermal-hydraulic codes such as RELAP5. The PARCS neutron code accepts libraries from HELIOS, TRITON, WIMS, SERPENT, etc., codes, but for some libraries is required special formatting. In the case of the SERPENT code, the GenPMAXS code must be used for the PARCS code to be able to read the cross sections library correctly. This work is part of a study on the PARCS/RELAP5 coupling for analyzing the control rod ejection of the Angra 2 reactor core. For this case, the core cross sections were obtained for 6 different branches varying the fuel temperature, moderator temperature, moderator density, boron concentration and considering rods removed and inserted. After obtaining the cross sections with the code SERPENT 2.1.26, these data were passed by a special formatting realized with the code GenPMAXS v6.2. Since GenPMAXS has several options controlling how to process the cross-sections generated by Serpent, a several doubts arose about the correct use of the code. When the doubts are answered, the file with the input data that will be used for the PARCS / RELAP coupling can be built.
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spelling 2020-01-15T18:38:07Z2020-01-15T18:38:07ZOctober 21-25, 2019http://repositorio.ipen.br/handle/123456789/307290000-0001-9544-4509The Purdue Advanced Reactor Core Simulator (PARCS) is a computer code that solves the time-dependent two-group neutron diffusion equation in three-dimensional Cartesian geometry using nodal methods to obtain the transient neutron flux distribution. The code is used in the analysis of reactivity-initiated accidents in light-water reactors where spatial effects may be important. It may be run in the stand-alone mode or coupled to other NRC thermal-hydraulic codes such as RELAP5. The PARCS neutron code accepts libraries from HELIOS, TRITON, WIMS, SERPENT, etc., codes, but for some libraries is required special formatting. In the case of the SERPENT code, the GenPMAXS code must be used for the PARCS code to be able to read the cross sections library correctly. This work is part of a study on the PARCS/RELAP5 coupling for analyzing the control rod ejection of the Angra 2 reactor core. For this case, the core cross sections were obtained for 6 different branches varying the fuel temperature, moderator temperature, moderator density, boron concentration and considering rods removed and inserted. After obtaining the cross sections with the code SERPENT 2.1.26, these data were passed by a special formatting realized with the code GenPMAXS v6.2. Since GenPMAXS has several options controlling how to process the cross-sections generated by Serpent, a several doubts arose about the correct use of the code. When the doubts are answered, the file with the input data that will be used for the PARCS / RELAP coupling can be built.Submitted by Celia Satomi Uehara (celia.u-topservice@ipen.br) on 2020-01-15T18:38:07Z No. of bitstreams: 1 26382.pdf: 333660 bytes, checksum: c429c8b519ace58ceb9a34da96f8884c (MD5)Made available in DSpace on 2020-01-15T18:38:07Z (GMT). No. of bitstreams: 1 26382.pdf: 333660 bytes, checksum: c429c8b519ace58ceb9a34da96f8884c (MD5)5503-5512Associa????o Brasileira de Energia Nuclearangra-2 reactorcomputerized simulationcontrol elementscouplingcross sectionsmonte carlo methodp codesreactor coresrod ejection accidentss codesThe cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS codeinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de JaneiroSantos, SP1908202600600SANCHEZ, ANDREACARLUCCIO, THIAGOSABUNDJIAN, GAIANEINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN263822019SABUNDJIAN, GAIANESANCHEZ, ANDREA20-01Proceedings2021908SABUNDJIAN, GAIANE:202:420:NSANCHEZ, ANDREA:1908:-1:SORIGINAL26382.pdf26382.pdfapplication/pdf333660http://repositorio.ipen.br/bitstream/123456789/30729/1/26382.pdfc429c8b519ace58ceb9a34da96f8884cMD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/30729/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/307292020-04-12 23:13:31.687oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102020-04-12T23:13:31Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code
title The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code
spellingShingle The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code
SANCHEZ, ANDREA
angra-2 reactor
computerized simulation
control elements
coupling
cross sections
monte carlo method
p codes
reactor cores
rod ejection accidents
s codes
title_short The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code
title_full The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code
title_fullStr The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code
title_full_unstemmed The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code
title_sort The cross sections obtained by the serpent code and formatting the input data for the PARCS code using the GenPMAXS code
author SANCHEZ, ANDREA
author_facet SANCHEZ, ANDREA
CARLUCCIO, THIAGO
SABUNDJIAN, GAIANE
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author_role author
author2 CARLUCCIO, THIAGO
SABUNDJIAN, GAIANE
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author2_role author
author
author
dc.contributor.author.fl_str_mv SANCHEZ, ANDREA
CARLUCCIO, THIAGO
SABUNDJIAN, GAIANE
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.subject.por.fl_str_mv angra-2 reactor
computerized simulation
control elements
coupling
cross sections
monte carlo method
p codes
reactor cores
rod ejection accidents
s codes
topic angra-2 reactor
computerized simulation
control elements
coupling
cross sections
monte carlo method
p codes
reactor cores
rod ejection accidents
s codes
description The Purdue Advanced Reactor Core Simulator (PARCS) is a computer code that solves the time-dependent two-group neutron diffusion equation in three-dimensional Cartesian geometry using nodal methods to obtain the transient neutron flux distribution. The code is used in the analysis of reactivity-initiated accidents in light-water reactors where spatial effects may be important. It may be run in the stand-alone mode or coupled to other NRC thermal-hydraulic codes such as RELAP5. The PARCS neutron code accepts libraries from HELIOS, TRITON, WIMS, SERPENT, etc., codes, but for some libraries is required special formatting. In the case of the SERPENT code, the GenPMAXS code must be used for the PARCS code to be able to read the cross sections library correctly. This work is part of a study on the PARCS/RELAP5 coupling for analyzing the control rod ejection of the Angra 2 reactor core. For this case, the core cross sections were obtained for 6 different branches varying the fuel temperature, moderator temperature, moderator density, boron concentration and considering rods removed and inserted. After obtaining the cross sections with the code SERPENT 2.1.26, these data were passed by a special formatting realized with the code GenPMAXS v6.2. Since GenPMAXS has several options controlling how to process the cross-sections generated by Serpent, a several doubts arose about the correct use of the code. When the doubts are answered, the file with the input data that will be used for the PARCS / RELAP coupling can be built.
publishDate 2020
dc.date.evento.pt_BR.fl_str_mv October 21-25, 2019
dc.date.accessioned.fl_str_mv 2020-01-15T18:38:07Z
dc.date.available.fl_str_mv 2020-01-15T18:38:07Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
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dc.publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
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