Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels
Autor(a) principal: | |
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Data de Publicação: | 2018 |
Outros Autores: | , , , |
Tipo de documento: | Artigo de conferência |
Idioma: | eng |
Título da fonte: | Repositório Institucional da UFMG |
Texto Completo: | http://hdl.handle.net/1843/57002 https://orcid.org/0000-0001-5999-9961 https://orcid.org/0000-0001-8618-8195 |
Resumo: | A spent fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses reprocessed fuels. PWR nuclear fuel assemblies with four types of fuels were considered: standard PWR fuel, MOX fuel, thorium-uranium fuel and reprocessed transuranic fuel spiked with thorium. The MOX and UO2 benchmark model was evaluated using SCALE 6.0 code with KENO-V transport code and then, adopted as a reference for other fuels compositions. The four fuel assemblies were submitted to irradiation at normal operation conditions. The burnup calculations were obtained using the TRITON sequence in the SCALE 6.0 code package. The fuel assemblies modeled use a benchmark 17x17 PWR fuel assembly dimensions. After irradiation, the fuels were inserted in the pool. The criticality safety limits were performed using the KENO-V transport code in the CSAS5 sequence. It was shown that mixing a quarter of reprocessed fuel withUO2 fuel in the pool, it would not need to be resized. |
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2023-07-26T17:00:20Z2023-07-26T17:00:20Z20184546555http://hdl.handle.net/1843/57002https://orcid.org/0000-0001-5999-9961https://orcid.org/0000-0001-8618-8195A spent fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses reprocessed fuels. PWR nuclear fuel assemblies with four types of fuels were considered: standard PWR fuel, MOX fuel, thorium-uranium fuel and reprocessed transuranic fuel spiked with thorium. The MOX and UO2 benchmark model was evaluated using SCALE 6.0 code with KENO-V transport code and then, adopted as a reference for other fuels compositions. The four fuel assemblies were submitted to irradiation at normal operation conditions. The burnup calculations were obtained using the TRITON sequence in the SCALE 6.0 code package. The fuel assemblies modeled use a benchmark 17x17 PWR fuel assembly dimensions. After irradiation, the fuels were inserted in the pool. The criticality safety limits were performed using the KENO-V transport code in the CSAS5 sequence. It was shown that mixing a quarter of reprocessed fuel withUO2 fuel in the pool, it would not need to be resized.Uma piscina de combustível usada de um Reator de Água Pressurizada (PWR) típico foi avaliada para estudos de criticidade quando usa combustíveis reprocessados. Foram considerados conjuntos de combustível nuclear PWR com quatro tipos de combustíveis: combustível PWR padrão, combustível MOX, combustível tório-urânio e combustível transurânico reprocessado com adição de tório. O modelo benchmark MOX e UO2 foi avaliado usando o código SCALE 6.0 com código de transporte KENO-V e, então, adotado como referência para outras composições de combustíveis. Os quatro conjuntos combustíveis foram submetidos à irradiação em condições normais de operação. Os cálculos de queima foram obtidos usando a sequência TRITON no pacote de código SCALE 6.0. Os conjuntos de combustível modelados usam dimensões de conjunto de combustível PWR de referência 17x17. Após a irradiação, os combustíveis foram inseridos na piscina. Os limites de segurança de criticalidade foram realizados usando o código de transporte KENO-V na sequência CSAS5. Foi demonstrado que misturar um quarto de combustível reprocessado com combustível UO2 na piscina não precisaria ser redimensionado.CNPq - Conselho Nacional de Desenvolvimento Científico e TecnológicoFAPEMIG - Fundação de Amparo à Pesquisa do Estado de Minas GeraisCAPES - Coordenação de Aperfeiçoamento de Pessoal de Nível SuperiorOutra AgênciaengUniversidade Federal de Minas GeraisUFMGBrasilENG - DEPARTAMENTO DE ENGENHARIA NUCLEARSemana de Engenharia Nuclear e Ciências das RadiaçõesReatores nuclearesReatores de água pressurizadaCombustíveis nuclearesCombustíveis para reatores nucleares - ReprocessamentoCriticalidade (Engenharia nuclear)CriticalitySpent fuel poolReprocessed fuelCriticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuelsAnálise de segurança de criticidade da piscina de combustível irradiado para um PWR usando combustíveis nucleares reprocessadosinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjecthttps://sencir.nuclear.ufmg.br/anais/Jéssica Achilles PimentelFabiano Cardoso da SilvaVictor Faria de CastroClaubia Pereira Bezerra LimaMaria Auxiliadora Fortini Velosoapplication/pdfinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional da UFMGinstname:Universidade Federal de Minas Gerais (UFMG)instacron:UFMGLICENSELicense.txtLicense.txttext/plain; charset=utf-82042https://repositorio.ufmg.br/bitstream/1843/57002/1/License.txtfa505098d172de0bc8864fc1287ffe22MD51ORIGINALCriticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels.pdfCriticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels.pdfapplication/pdf399987https://repositorio.ufmg.br/bitstream/1843/57002/2/Criticality%20safety%20analysis%20of%20spent%20fuel%20pool%20for%20a%20PWR%20using%20reprocessed%20nuclear%20fuels.pdf1863f20e1fbed78cc9b273d469679247MD521843/570022023-07-26 14:00:20.823oai:repositorio.ufmg.br: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Repositório de PublicaçõesPUBhttps://repositorio.ufmg.br/oaiopendoar:2023-07-26T17:00:20Repositório Institucional da UFMG - Universidade Federal de Minas Gerais (UFMG)false |
dc.title.pt_BR.fl_str_mv |
Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels |
dc.title.alternative.pt_BR.fl_str_mv |
Análise de segurança de criticidade da piscina de combustível irradiado para um PWR usando combustíveis nucleares reprocessados |
title |
Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels |
spellingShingle |
Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels Jéssica Achilles Pimentel Criticality Spent fuel pool Reprocessed fuel Reatores nucleares Reatores de água pressurizada Combustíveis nucleares Combustíveis para reatores nucleares - Reprocessamento Criticalidade (Engenharia nuclear) |
title_short |
Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels |
title_full |
Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels |
title_fullStr |
Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels |
title_full_unstemmed |
Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels |
title_sort |
Criticality safety analysis of spent fuel pool for a PWR using reprocessed nuclear fuels |
author |
Jéssica Achilles Pimentel |
author_facet |
Jéssica Achilles Pimentel Fabiano Cardoso da Silva Victor Faria de Castro Claubia Pereira Bezerra Lima Maria Auxiliadora Fortini Veloso |
author_role |
author |
author2 |
Fabiano Cardoso da Silva Victor Faria de Castro Claubia Pereira Bezerra Lima Maria Auxiliadora Fortini Veloso |
author2_role |
author author author author |
dc.contributor.author.fl_str_mv |
Jéssica Achilles Pimentel Fabiano Cardoso da Silva Victor Faria de Castro Claubia Pereira Bezerra Lima Maria Auxiliadora Fortini Veloso |
dc.subject.por.fl_str_mv |
Criticality Spent fuel pool Reprocessed fuel |
topic |
Criticality Spent fuel pool Reprocessed fuel Reatores nucleares Reatores de água pressurizada Combustíveis nucleares Combustíveis para reatores nucleares - Reprocessamento Criticalidade (Engenharia nuclear) |
dc.subject.other.pt_BR.fl_str_mv |
Reatores nucleares Reatores de água pressurizada Combustíveis nucleares Combustíveis para reatores nucleares - Reprocessamento Criticalidade (Engenharia nuclear) |
description |
A spent fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses reprocessed fuels. PWR nuclear fuel assemblies with four types of fuels were considered: standard PWR fuel, MOX fuel, thorium-uranium fuel and reprocessed transuranic fuel spiked with thorium. The MOX and UO2 benchmark model was evaluated using SCALE 6.0 code with KENO-V transport code and then, adopted as a reference for other fuels compositions. The four fuel assemblies were submitted to irradiation at normal operation conditions. The burnup calculations were obtained using the TRITON sequence in the SCALE 6.0 code package. The fuel assemblies modeled use a benchmark 17x17 PWR fuel assembly dimensions. After irradiation, the fuels were inserted in the pool. The criticality safety limits were performed using the KENO-V transport code in the CSAS5 sequence. It was shown that mixing a quarter of reprocessed fuel withUO2 fuel in the pool, it would not need to be resized. |
publishDate |
2018 |
dc.date.issued.fl_str_mv |
2018 |
dc.date.accessioned.fl_str_mv |
2023-07-26T17:00:20Z |
dc.date.available.fl_str_mv |
2023-07-26T17:00:20Z |
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://hdl.handle.net/1843/57002 |
dc.identifier.orcid.pt_BR.fl_str_mv |
https://orcid.org/0000-0001-5999-9961 https://orcid.org/0000-0001-8618-8195 |
url |
http://hdl.handle.net/1843/57002 https://orcid.org/0000-0001-5999-9961 https://orcid.org/0000-0001-8618-8195 |
dc.language.iso.fl_str_mv |
eng |
language |
eng |
dc.relation.ispartof.pt_BR.fl_str_mv |
Semana de Engenharia Nuclear e Ciências das Radiações |
dc.rights.driver.fl_str_mv |
info:eu-repo/semantics/openAccess |
eu_rights_str_mv |
openAccess |
dc.format.none.fl_str_mv |
application/pdf |
dc.publisher.none.fl_str_mv |
Universidade Federal de Minas Gerais |
dc.publisher.initials.fl_str_mv |
UFMG |
dc.publisher.country.fl_str_mv |
Brasil |
dc.publisher.department.fl_str_mv |
ENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR |
publisher.none.fl_str_mv |
Universidade Federal de Minas Gerais |
dc.source.none.fl_str_mv |
reponame:Repositório Institucional da UFMG instname:Universidade Federal de Minas Gerais (UFMG) instacron:UFMG |
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Universidade Federal de Minas Gerais (UFMG) |
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UFMG |
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UFMG |
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Repositório Institucional da UFMG |
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Repositório Institucional da UFMG |
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