Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE

[EN] In this work the fundamentals and application results of an uncertainty analysis of a loss of coolant and loss of cooling accident in a spent fuel pool are presented. The spent fuel pool was modeled with TRACE V5.0 Patch 5 using a VESSEL 3D component in Cartesian coordinates. A more detailed no...

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Autores: Sanchez Saez, Francisco|||0000-0002-3011-9884, Carlos Alberola, Sofía|||0000-0002-0637-325X, Villanueva López, José Felipe|||0000-0002-7684-6884, Sánchez Galdón, Ana Isabel|||0000-0002-3159-8020, Martorell Alsina, Sebastián Salvador|||0000-0003-1706-4740
Tipo de recurso: artículo
Fecha de publicación:2020
País:España
Institución:Universitat Politècnica de València (UPV)
Repositorio:RiuNet. Repositorio Institucional de la Universitat Politécnica de Valéncia
Idioma:inglés
OAI Identifier:oai:riunet.upv.es:10251/193943
Acceso en línea:https://riunet.upv.es/handle/10251/193943
Access Level:acceso abierto
Palabra clave:Spent fuel pool
TRACE
Elastic Net
LASSO regression
Uncertainty analysis
Wilks
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
07.- Asegurar el acceso a energías asequibles, fiables, sostenibles y modernas para todos
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network_acronym_str ES
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repository_id_str
spelling Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACESanchez Saez, Francisco|||0000-0002-3011-9884Carlos Alberola, Sofía|||0000-0002-0637-325XVillanueva López, José Felipe|||0000-0002-7684-6884Sánchez Galdón, Ana Isabel|||0000-0002-3159-8020Martorell Alsina, Sebastián Salvador|||0000-0003-1706-4740Spent fuel poolTRACEElastic NetLASSO regressionUncertainty analysisWilksESTADISTICA E INVESTIGACION OPERATIVAINGENIERIA NUCLEAR07.- Asegurar el acceso a energías asequibles, fiables, sostenibles y modernas para todos[EN] In this work the fundamentals and application results of an uncertainty analysis of a loss of coolant and loss of cooling accident in a spent fuel pool are presented. The spent fuel pool was modeled with TRACE V5.0 Patch 5 using a VESSEL 3D component in Cartesian coordinates. A more detailed nodalization was necessary as compared with a previous study of the same accident scenario to better develop the uncertainty analysis in the framework of the Best Estimate Plus Uncertainty (BEPU) approach. First, the model was calibrated using Main Yankee spent fuel pool experimental data of temperatures and flows measured in steady state conditions. Using the calibrated model, the analysis of the accident was performed considering uncertainty in boundary conditions and in all the coefficients included in the TRACE uncertainty quantification data module. The figure of merit selected in this work is the time at which the cladding oxidation reaches 0.17 times the cladding thickness before oxidation (CFR 50.46 b2). The uncertainty analysis was performed using Wilks' method and surrogate models. In particular, the Elastic Net surrogate model has demonstrated its potential not only to predict the evolution of the figure of merit in an appropriate way with lower computational effort than the Wilks' method but also its capability to identify the most relevant uncertain parameters, such as the fuel and cladding specific heats, rod internal pressure coefficient, burst temperature coefficient, a group of fluid regime heat transfer coefficients, the cladding metal-water reaction rate coefficient and the cladding tolerance for the average cores. In addition, the surrogate model provides more information of the distribution of the evolution of the figure of merit. The estimations of the 5/95 tolerance limits, both with the Wilks' method and with the surrogate models, are very similar, ranging from 30.432 to 30.461 h.The authors are grateful to the Spanish "Consejo de Seguridad Nuclear (CSN)" for the financial support they provided for Research MASA Project 2 and STN/4524/2015/640 (CAMP Project).ElsevierDepartamento de Ingeniería Química y NuclearDepartamento de Estadística e Investigación Operativa Aplicadas y CalidadEscuela Técnica Superior de Ingeniería IndustrialEscuela Técnica Superior de Ingeniería InformáticaGrupo de Medioambiente y Seguridad Industrial. MEDASEGIConsejo de Seguridad NuclearRepositorio Institucional de la Universitat Politècnica de València Riunet20202020-06-01journal articlehttp://purl.org/coar/resource_type/c_6501VoRhttp://purl.org/coar/version/c_970fb48d4fbd8a85info:eu-repo/semantics/articleapplication/pdfapplication/pdfhttps://riunet.upv.es/handle/10251/193943reponame:RiuNet. Repositorio Institucional de la Universitat Politécnica de Valénciainstname:Universitat Politècnica de València (UPV)InglésengCONSEJO DE SEGURIDAD NUCLEAR CONSEJO DE SEGURIDAD NUCLEAR STN%2F4524%2F2015%2F640 ACUERDO ESPECIFICO DE COLABORACION CSN-UPV-UPC-UPM CAMP ESPAÑACONSEJO DE SEGURIDAD NUCLEAR CONSEJO DE SEGURIDAD NUCLEAR MASA-2 METODOS AVANZADOS DE SIMULACION Y ANALISIS EN EL CAMPO DE LA SEGURIDAD NUCLEAR, SEGUNDA PARTEopen accesshttp://purl.org/coar/access_right/c_abf2Reconocimiento - No comercial - Sin obra derivada (by-nc-nd) http://creativecommons.org/licenses/by-nc-nd/4.0/info:eu-repo/semantics/openAccessoai:riunet.upv.es:10251/1939432026-06-13T07:49:27Z
dc.title.none.fl_str_mv Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
title Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
spellingShingle Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
Sanchez Saez, Francisco|||0000-0002-3011-9884
Spent fuel pool
TRACE
Elastic Net
LASSO regression
Uncertainty analysis
Wilks
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
07.- Asegurar el acceso a energías asequibles, fiables, sostenibles y modernas para todos
title_short Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
title_full Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
title_fullStr Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
title_full_unstemmed Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
title_sort Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE
dc.creator.none.fl_str_mv Sanchez Saez, Francisco|||0000-0002-3011-9884
Carlos Alberola, Sofía|||0000-0002-0637-325X
Villanueva López, José Felipe|||0000-0002-7684-6884
Sánchez Galdón, Ana Isabel|||0000-0002-3159-8020
Martorell Alsina, Sebastián Salvador|||0000-0003-1706-4740
author Sanchez Saez, Francisco|||0000-0002-3011-9884
author_facet Sanchez Saez, Francisco|||0000-0002-3011-9884
Carlos Alberola, Sofía|||0000-0002-0637-325X
Villanueva López, José Felipe|||0000-0002-7684-6884
Sánchez Galdón, Ana Isabel|||0000-0002-3159-8020
Martorell Alsina, Sebastián Salvador|||0000-0003-1706-4740
author_role author
author2 Carlos Alberola, Sofía|||0000-0002-0637-325X
Villanueva López, José Felipe|||0000-0002-7684-6884
Sánchez Galdón, Ana Isabel|||0000-0002-3159-8020
Martorell Alsina, Sebastián Salvador|||0000-0003-1706-4740
author2_role author
author
author
author
dc.contributor.none.fl_str_mv Departamento de Ingeniería Química y Nuclear
Departamento de Estadística e Investigación Operativa Aplicadas y Calidad
Escuela Técnica Superior de Ingeniería Industrial
Escuela Técnica Superior de Ingeniería Informática
Grupo de Medioambiente y Seguridad Industrial. MEDASEGI
Consejo de Seguridad Nuclear
Repositorio Institucional de la Universitat Politècnica de València Riunet
dc.subject.none.fl_str_mv Spent fuel pool
TRACE
Elastic Net
LASSO regression
Uncertainty analysis
Wilks
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
07.- Asegurar el acceso a energías asequibles, fiables, sostenibles y modernas para todos
topic Spent fuel pool
TRACE
Elastic Net
LASSO regression
Uncertainty analysis
Wilks
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
07.- Asegurar el acceso a energías asequibles, fiables, sostenibles y modernas para todos
description [EN] In this work the fundamentals and application results of an uncertainty analysis of a loss of coolant and loss of cooling accident in a spent fuel pool are presented. The spent fuel pool was modeled with TRACE V5.0 Patch 5 using a VESSEL 3D component in Cartesian coordinates. A more detailed nodalization was necessary as compared with a previous study of the same accident scenario to better develop the uncertainty analysis in the framework of the Best Estimate Plus Uncertainty (BEPU) approach. First, the model was calibrated using Main Yankee spent fuel pool experimental data of temperatures and flows measured in steady state conditions. Using the calibrated model, the analysis of the accident was performed considering uncertainty in boundary conditions and in all the coefficients included in the TRACE uncertainty quantification data module. The figure of merit selected in this work is the time at which the cladding oxidation reaches 0.17 times the cladding thickness before oxidation (CFR 50.46 b2). The uncertainty analysis was performed using Wilks' method and surrogate models. In particular, the Elastic Net surrogate model has demonstrated its potential not only to predict the evolution of the figure of merit in an appropriate way with lower computational effort than the Wilks' method but also its capability to identify the most relevant uncertain parameters, such as the fuel and cladding specific heats, rod internal pressure coefficient, burst temperature coefficient, a group of fluid regime heat transfer coefficients, the cladding metal-water reaction rate coefficient and the cladding tolerance for the average cores. In addition, the surrogate model provides more information of the distribution of the evolution of the figure of merit. The estimations of the 5/95 tolerance limits, both with the Wilks' method and with the surrogate models, are very similar, ranging from 30.432 to 30.461 h.
publishDate 2020
dc.date.none.fl_str_mv 2020
2020-06-01
dc.type.none.fl_str_mv journal article
http://purl.org/coar/resource_type/c_6501
VoR
http://purl.org/coar/version/c_970fb48d4fbd8a85
dc.type.openaire.fl_str_mv info:eu-repo/semantics/article
format article
dc.identifier.none.fl_str_mv https://riunet.upv.es/handle/10251/193943
url https://riunet.upv.es/handle/10251/193943
dc.language.none.fl_str_mv Inglés
eng
language_invalid_str_mv Inglés
language eng
dc.relation.none.fl_str_mv CONSEJO DE SEGURIDAD NUCLEAR CONSEJO DE SEGURIDAD NUCLEAR STN%2F4524%2F2015%2F640 ACUERDO ESPECIFICO DE COLABORACION CSN-UPV-UPC-UPM CAMP ESPAÑA
CONSEJO DE SEGURIDAD NUCLEAR CONSEJO DE SEGURIDAD NUCLEAR MASA-2 METODOS AVANZADOS DE SIMULACION Y ANALISIS EN EL CAMPO DE LA SEGURIDAD NUCLEAR, SEGUNDA PARTE
dc.rights.none.fl_str_mv open access
http://purl.org/coar/access_right/c_abf2
Reconocimiento - No comercial - Sin obra derivada (by-nc-nd)
http://creativecommons.org/licenses/by-nc-nd/4.0/
dc.rights.openaire.fl_str_mv info:eu-repo/semantics/openAccess
rights_invalid_str_mv open access
http://purl.org/coar/access_right/c_abf2
Reconocimiento - No comercial - Sin obra derivada (by-nc-nd)
http://creativecommons.org/licenses/by-nc-nd/4.0/
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv Elsevier
publisher.none.fl_str_mv Elsevier
dc.source.none.fl_str_mv reponame:RiuNet. Repositorio Institucional de la Universitat Politécnica de Valéncia
instname:Universitat Politècnica de València (UPV)
instname_str Universitat Politècnica de València (UPV)
reponame_str RiuNet. Repositorio Institucional de la Universitat Politécnica de Valéncia
collection RiuNet. Repositorio Institucional de la Universitat Politécnica de Valéncia
repository.name.fl_str_mv
repository.mail.fl_str_mv
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score 15,301603

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