Benchmark Beavrs-PWR analysis using WIMS and PARCS codes
Autor(a) principal: | |
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Data de Publicação: | 2022 |
Outros Autores: | , , |
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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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 |
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 |
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