Benchmark Beavrs-PWR analysis using WIMS and PARCS codes

Detalhes bibliográficos
Autor(a) principal: Wilmer Aruquipa
Data de Publicação: 2022
Outros Autores: Patrícia Amélia de Lima Reis, Clarysson Alberto Mello da Silva, Claubia Pereira Bezerra Lima
Tipo de documento: Artigo de conferência
Idioma: por
Título da fonte: Repositório Institucional da UFMG
Texto Completo: http://hdl.handle.net/1843/60745
https://orcid.org/0000-0001-6782-8329
https://orcid.org/0000-0002-3082-644X
https://orcid.org/0000-0001-5999-9961
Resumo: Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), this article presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. The results show a small difference, in the case of the k-eff's values, the maximum standard deviation is 0.00466. All calculations were made for the reactor's Hot Zero Power status.
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spelling 2023-11-09T21:40:17Z2023-11-09T21:40:17Z2022510.29327/advs2021.4591889786559415762http://hdl.handle.net/1843/60745https://orcid.org/0000-0001-6782-8329https://orcid.org/0000-0002-3082-644Xhttps://orcid.org/0000-0001-5999-9961Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), this article presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. The results show a small difference, in the case of the k-eff's values, the maximum standard deviation is 0.00466. All calculations were made for the reactor's Hot Zero Power status.Baseado no BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) que contém especificações de referência para dados operacionais e medições para um reator de água pressurizada (PWR), este artigo apresenta um modelo para obtenção de seções transversais macroscópicas para os diferentes conjuntos de combustíveis do BEAVRS usando o WIMS. A biblioteca de dados de seção transversal microscópica utilizada foi ENDF/B-VI. Para o método de cálculo da seção transversal, foi considerada a abordagem do modelo multicelular, e os resultados foram comparados com outros trabalhos de referência. Esta metodologia visa validar o modelo de cálculo das seções transversais, e assim, avaliar se tal metodologia gera resultados válidos. Além disso, neste trabalho, as seções transversais macroscópicas geradas pelo WIMS foram utilizadas para simular o núcleo do reator de um PWR típico no PARCS. Os resultados mostram uma pequena diferença, no caso dos valores de k-eff o desvio padrão máximo é 0,00466. Todos os cálculos foram feitos para o status Hot Zero Power do reator.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 SuperiorporUniversidade Federal de Minas GeraisUFMGBrasilENG - DEPARTAMENTO DE ENGENHARIA NUCLEARSemana nacional de engenharia nuclear e da energia e ciências das radiaçõesReatores de agua pressurizadaCombustíveis nuclearesTecnologia nuclearBEAVRSPARCSWIMSPWRCross SectionBenchmark Beavrs-PWR analysis using WIMS and PARCS codesAnálise de benchmark Beavrs-PWR usando códigos WIMS e PARCSinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjecthttps://www.even3.com.br/anais/advs2021/459188-benchmark-beavrs-pwr-analysis-using-wims-and-parcs-codes/Wilmer AruquipaPatrícia Amélia de Lima ReisClarysson Alberto Mello da SilvaClaubia Pereira Bezerra Limaapplication/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/1843/60745/1/License.txtfa505098d172de0bc8864fc1287ffe22MD51ORIGINALBenchmark Beavrs-PWR analysis using WIMS and PARCS codes.pdfBenchmark Beavrs-PWR analysis using WIMS and PARCS codes.pdfapplication/pdf725339https://repositorio.ufmg.br/bitstream/1843/60745/2/Benchmark%20Beavrs-PWR%20analysis%20using%20WIMS%20and%20PARCS%20codes.pdf1ce76a0871eda8539e0ac5923e774d77MD521843/607452023-11-09 18:40:17.469oai:repositorio.ufmg.br:1843/60745Repositório de PublicaçõesPUBhttps://repositorio.ufmg.br/oaiopendoar:2023-11-09T21:40:17Repositório Institucional da UFMG - Universidade Federal de Minas Gerais (UFMG)false
dc.title.pt_BR.fl_str_mv Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
dc.title.alternative.pt_BR.fl_str_mv Análise de benchmark Beavrs-PWR usando códigos WIMS e PARCS
title Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
spellingShingle Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
Wilmer Aruquipa
BEAVRS
PARCS
WIMS
PWR
Cross Section
Reatores de agua pressurizada
Combustíveis nucleares
Tecnologia nuclear
title_short Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
title_full Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
title_fullStr Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
title_full_unstemmed Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
title_sort Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
author Wilmer Aruquipa
author_facet Wilmer Aruquipa
Patrícia Amélia de Lima Reis
Clarysson Alberto Mello da Silva
Claubia Pereira Bezerra Lima
author_role author
author2 Patrícia Amélia de Lima Reis
Clarysson Alberto Mello da Silva
Claubia Pereira Bezerra Lima
author2_role author
author
author
dc.contributor.author.fl_str_mv Wilmer Aruquipa
Patrícia Amélia de Lima Reis
Clarysson Alberto Mello da Silva
Claubia Pereira Bezerra Lima
dc.subject.por.fl_str_mv BEAVRS
PARCS
WIMS
PWR
Cross Section
topic BEAVRS
PARCS
WIMS
PWR
Cross Section
Reatores de agua pressurizada
Combustíveis nucleares
Tecnologia nuclear
dc.subject.other.pt_BR.fl_str_mv Reatores de agua pressurizada
Combustíveis nucleares
Tecnologia nuclear
description Based on the BEAVRS Benchmark (Benchmark for Evaluation And Validation of Reactor Simulations) which contains reference specifications for operational data and measurements for a pressurized water reactor (PWR), this article presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS. The microscopic cross section data library used was ENDF/B-VI. For the cross-section calculation method, the multicellular model approach was considered, and the results were compared with other reference works. This methodology aims to validate the model of calculation of the cross sections, and thus, evaluate whether such methodology generates valid results. Also, in this work, the macroscopic cross-sections generated by WIMS were used to simulate the reactor core of a typical PWR in PARCS. The results show a small difference, in the case of the k-eff's values, the maximum standard deviation is 0.00466. All calculations were made for the reactor's Hot Zero Power status.
publishDate 2022
dc.date.issued.fl_str_mv 2022
dc.date.accessioned.fl_str_mv 2023-11-09T21:40:17Z
dc.date.available.fl_str_mv 2023-11-09T21:40:17Z
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/1843/60745
dc.identifier.doi.pt_BR.fl_str_mv 10.29327/advs2021.459188
dc.identifier.isbn.pt_BR.fl_str_mv 9786559415762
dc.identifier.orcid.pt_BR.fl_str_mv https://orcid.org/0000-0001-6782-8329
https://orcid.org/0000-0002-3082-644X
https://orcid.org/0000-0001-5999-9961
identifier_str_mv 10.29327/advs2021.459188
9786559415762
url http://hdl.handle.net/1843/60745
https://orcid.org/0000-0001-6782-8329
https://orcid.org/0000-0002-3082-644X
https://orcid.org/0000-0001-5999-9961
dc.language.iso.fl_str_mv por
language por
dc.relation.ispartof.pt_BR.fl_str_mv Semana nacional de engenharia nuclear e da energia e ciências das radiações
dc.rights.driver.fl_str_mv info:eu-repo/semantics/openAccess
eu_rights_str_mv openAccess
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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
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institution UFMG
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