Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production

Detalhes bibliográficos
Autor(a) principal: STEFANI, GIOVANNI L. de
Data de Publicação: 2020
Outros Autores: GENEZINI, FREDERICO A., MOREIRA, JO??O M. de L., SANTOS, THIAGO A. dos, INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/30693
Resumo: In this work a parametric study was carried out to increase the production of radioisotopes in the IEA-R1 reactor. One of the variables directly proportional to isotope production is the magnitude of the neutron flux in which some material is exposed, so the main objective of this work was to increase neutron flux, especially in the center of the reactor in the beryllium element irradiator (EIBe), within the operational and safety limits of the reactor. The study is initiated by defining a default configuration, in which core of the IEA-R1 reactor is modeled with all fresh fuel assemblies to ensure the reduction of variables that affect the data analysis, then para metric studies were performed evaluating, by comparative analysis of the behavior of the relation of neutron flux versus the fuel for the standard configuration. Therefore, another configuration was tested: the changes in the core of graphite reflecting elements for beryllium, as well as, the result due to reactor core compaction. Parameters such as the fraction of delayed neutrons (Beff) and temperature reactivity coefficient are analyzed to ensure that the configuration has the minimum safety requirements for the reactor safe operation. The results of the study demonstrate a large increase in neutron flux magnitude and in particular in the center of the nucleus in the beryllium irradiating element.
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spelling 2020-01-15T00:06:08Z2020-01-15T00:06:08ZOctober 21-25, 2019http://repositorio.ipen.br/handle/123456789/306930000-0002-6318-6805In this work a parametric study was carried out to increase the production of radioisotopes in the IEA-R1 reactor. One of the variables directly proportional to isotope production is the magnitude of the neutron flux in which some material is exposed, so the main objective of this work was to increase neutron flux, especially in the center of the reactor in the beryllium element irradiator (EIBe), within the operational and safety limits of the reactor. The study is initiated by defining a default configuration, in which core of the IEA-R1 reactor is modeled with all fresh fuel assemblies to ensure the reduction of variables that affect the data analysis, then para metric studies were performed evaluating, by comparative analysis of the behavior of the relation of neutron flux versus the fuel for the standard configuration. Therefore, another configuration was tested: the changes in the core of graphite reflecting elements for beryllium, as well as, the result due to reactor core compaction. Parameters such as the fraction of delayed neutrons (Beff) and temperature reactivity coefficient are analyzed to ensure that the configuration has the minimum safety requirements for the reactor safe operation. The results of the study demonstrate a large increase in neutron flux magnitude and in particular in the center of the nucleus in the beryllium irradiating element.Submitted by Celia Satomi Uehara (celia.u-topservice@ipen.br) on 2020-01-15T00:06:08Z No. of bitstreams: 1 26342.pdf: 880998 bytes, checksum: 7eba90ad48b45a35d474f1d8ae975907 (MD5)Made available in DSpace on 2020-01-15T00:06:08Z (GMT). No. of bitstreams: 1 26342.pdf: 880998 bytes, checksum: 7eba90ad48b45a35d474f1d8ae975907 (MD5)4164-4176Associa????o Brasileira de Energia Nuclearberylliumdelayed neutronsfuel assembliesfuel consumptioniear-1 reactorisotope productionneutron fluxoptimizationparametric analysisreactivity coefficientsreactor coresthermal neutronsOptimization on the core of IEA-R1 research reactor for enhance the radioisotopes productioninfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de JaneiroSantos, SP760620458783600600600STEFANI, GIOVANNI L. deGENEZINI, FREDERICO A.MOREIRA, JO??O M. de L.SANTOS, THIAGO A. dosINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN263422019SANTOS, THIAGO A. dosGENEZINI, FREDERICO A.STEFANI, GIOVANNI L. de20-01Proceedings878320457606SANTOS, THIAGO A. dos:8783:310:NGENEZINI, FREDERICO A.:2045:310:NSTEFANI, GIOVANNI L. de:7606:310:SORIGINAL26342.pdf26342.pdfapplication/pdf880998http://repositorio.ipen.br/bitstream/123456789/30693/1/26342.pdf7eba90ad48b45a35d474f1d8ae975907MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/30693/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/306932020-03-23 14:29:24.718oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102020-03-23T14:29:24Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
title Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
spellingShingle Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
STEFANI, GIOVANNI L. de
beryllium
delayed neutrons
fuel assemblies
fuel consumption
iear-1 reactor
isotope production
neutron flux
optimization
parametric analysis
reactivity coefficients
reactor cores
thermal neutrons
title_short Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
title_full Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
title_fullStr Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
title_full_unstemmed Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
title_sort Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
author STEFANI, GIOVANNI L. de
author_facet STEFANI, GIOVANNI L. de
GENEZINI, FREDERICO A.
MOREIRA, JO??O M. de L.
SANTOS, THIAGO A. dos
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author_role author
author2 GENEZINI, FREDERICO A.
MOREIRA, JO??O M. de L.
SANTOS, THIAGO A. dos
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author2_role author
author
author
author
dc.contributor.author.fl_str_mv STEFANI, GIOVANNI L. de
GENEZINI, FREDERICO A.
MOREIRA, JO??O M. de L.
SANTOS, THIAGO A. dos
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.subject.por.fl_str_mv beryllium
delayed neutrons
fuel assemblies
fuel consumption
iear-1 reactor
isotope production
neutron flux
optimization
parametric analysis
reactivity coefficients
reactor cores
thermal neutrons
topic beryllium
delayed neutrons
fuel assemblies
fuel consumption
iear-1 reactor
isotope production
neutron flux
optimization
parametric analysis
reactivity coefficients
reactor cores
thermal neutrons
description In this work a parametric study was carried out to increase the production of radioisotopes in the IEA-R1 reactor. One of the variables directly proportional to isotope production is the magnitude of the neutron flux in which some material is exposed, so the main objective of this work was to increase neutron flux, especially in the center of the reactor in the beryllium element irradiator (EIBe), within the operational and safety limits of the reactor. The study is initiated by defining a default configuration, in which core of the IEA-R1 reactor is modeled with all fresh fuel assemblies to ensure the reduction of variables that affect the data analysis, then para metric studies were performed evaluating, by comparative analysis of the behavior of the relation of neutron flux versus the fuel for the standard configuration. Therefore, another configuration was tested: the changes in the core of graphite reflecting elements for beryllium, as well as, the result due to reactor core compaction. Parameters such as the fraction of delayed neutrons (Beff) and temperature reactivity coefficient are analyzed to ensure that the configuration has the minimum safety requirements for the reactor safe operation. The results of the study demonstrate a large increase in neutron flux magnitude and in particular in the center of the nucleus in the beryllium irradiating element.
publishDate 2020
dc.date.evento.pt_BR.fl_str_mv October 21-25, 2019
dc.date.accessioned.fl_str_mv 2020-01-15T00:06:08Z
dc.date.available.fl_str_mv 2020-01-15T00:06:08Z
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/123456789/30693
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dc.publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
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