Macroscopic cross section generation with WIMS-ANL for a PWR

Detalhes bibliográficos
Autor(a) principal: Wilmer Aruquipa Coloma
Data de Publicação: 2022
Outros Autores: Patrícia Amélia de Lima Reis, Clarysson Alberto Mello da Silva, Claubia Pereira Bezerra Lima
Tipo de documento: Artigo
Idioma: eng
Título da fonte: Repositório Institucional da UFMG
Texto Completo: https://doi.org/10.15392/2319-0612.2022.1948
http://hdl.handle.net/1843/60676
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), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. 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. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation.
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spelling 2023-11-08T22:20:17Z2023-11-08T22:20:17Z2022103Ahttps://doi.org/10.15392/2319-0612.2022.19482319-0612http://hdl.handle.net/1843/60676https://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), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. 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. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation.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), apresenta um modelo para obtenção de seções transversais macroscópicas para os diferentes conjuntos de combustíveis do BEAVRS usando o WIMS-ANL. 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. Todos os cálculos foram feitos para o status Hot Zero Power do reator e para o primeiro ciclo de operação.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 SuperiorengUniversidade Federal de Minas GeraisUFMGBrasilENG - DEPARTAMENTO DE ENGENHARIA NUCLEARBrazilian journal of radiation scienceEngenharia nuclearReatores de água pressurizadaReatores nuclearesMacroscopic cross sectionsBEAVRSPWRMacroscopic cross section generation with WIMS-ANL for a PWRGeração de seção transversal macroscópica com WIMS-ANL para um PWRinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/articlehttps://bjrs.org.br/revista/index.php/REVISTA/article/view/1948Wilmer Aruquipa ColomaPatrícia 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/1843/60676/1/License.txtfa505098d172de0bc8864fc1287ffe22MD51ORIGINALMacroscopic cross section generation with WIMS-ANL for a PWR.pdfMacroscopic cross section generation with WIMS-ANL for a PWR.pdfapplication/pdf642456https://repositorio.ufmg.br/bitstream/1843/60676/2/Macroscopic%20cross%20section%20generation%20with%20WIMS-ANL%20for%20a%20PWR.pdfa348aba169fd14f8b227692c2ec0fcd0MD521843/606762023-11-08 19:20:18.204oai:repositorio.ufmg.br:1843/60676Repositório de PublicaçõesPUBhttps://repositorio.ufmg.br/oaiopendoar:2023-11-08T22:20:18Repositório Institucional da UFMG - Universidade Federal de Minas Gerais (UFMG)false
dc.title.pt_BR.fl_str_mv Macroscopic cross section generation with WIMS-ANL for a PWR
dc.title.alternative.pt_BR.fl_str_mv Geração de seção transversal macroscópica com WIMS-ANL para um PWR
title Macroscopic cross section generation with WIMS-ANL for a PWR
spellingShingle Macroscopic cross section generation with WIMS-ANL for a PWR
Wilmer Aruquipa Coloma
Macroscopic cross sections
BEAVRS
PWR
Engenharia nuclear
Reatores de água pressurizada
Reatores nucleares
title_short Macroscopic cross section generation with WIMS-ANL for a PWR
title_full Macroscopic cross section generation with WIMS-ANL for a PWR
title_fullStr Macroscopic cross section generation with WIMS-ANL for a PWR
title_full_unstemmed Macroscopic cross section generation with WIMS-ANL for a PWR
title_sort Macroscopic cross section generation with WIMS-ANL for a PWR
author Wilmer Aruquipa Coloma
author_facet Wilmer Aruquipa Coloma
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 Coloma
Patrícia Amélia de Lima Reis
Clarysson Alberto Mello da Silva
Claubia Pereira Bezerra Lima
dc.subject.por.fl_str_mv Macroscopic cross sections
BEAVRS
PWR
topic Macroscopic cross sections
BEAVRS
PWR
Engenharia nuclear
Reatores de água pressurizada
Reatores nucleares
dc.subject.other.pt_BR.fl_str_mv Engenharia nuclear
Reatores de água pressurizada
Reatores nucleares
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), it presents a model for obtaining macroscopic cross sections for the different fuels assemblies of BEAVRS using the WIMS-ANL. 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. All calculations were made for the reactor's Hot Zero Power status and the first cycle of operation.
publishDate 2022
dc.date.issued.fl_str_mv 2022
dc.date.accessioned.fl_str_mv 2023-11-08T22:20:17Z
dc.date.available.fl_str_mv 2023-11-08T22:20:17Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
dc.type.driver.fl_str_mv info:eu-repo/semantics/article
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status_str publishedVersion
dc.identifier.uri.fl_str_mv http://hdl.handle.net/1843/60676
dc.identifier.doi.pt_BR.fl_str_mv https://doi.org/10.15392/2319-0612.2022.1948
dc.identifier.issn.pt_BR.fl_str_mv 2319-0612
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
url https://doi.org/10.15392/2319-0612.2022.1948
http://hdl.handle.net/1843/60676
https://orcid.org/0000-0001-6782-8329
https://orcid.org/0000-0002-3082-644X
https://orcid.org/0000-0001-5999-9961
identifier_str_mv 2319-0612
dc.language.iso.fl_str_mv eng
language eng
dc.relation.ispartof.pt_BR.fl_str_mv Brazilian journal of radiation science
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
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