Macroscopic cross section generation with WIMS-ANL for a PWR
Autor(a) principal: | |
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Data de Publicação: | 2022 |
Outros Autores: | , , |
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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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 |
format |
article |
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 |
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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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