Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods

[EN] The Nuclear Energy Agency auspices simulation of experiments in different facilities under several programs. One on them consisted of performing a counterpart test between ROSA/LSTF and PKL facilities, with the main objective of determining the effectiveness of late accident management actions...

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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:2017
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:10251/102267
Acceso en línea:https://riunet.upv.es/handle/10251/102267
Access Level:acceso abierto
Palabra clave:Uncertainty
PKL
Cladding temperature
TRACE
Wilks
GAM
BEPU
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
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spelling Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methodsSanchez 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|||0000-0003-1706-4740UncertaintyPKLCladding temperatureTRACEWilksGAMBEPUESTADISTICA E INVESTIGACION OPERATIVAINGENIERIA NUCLEAR[EN] The Nuclear Energy Agency auspices simulation of experiments in different facilities under several programs. One on them consisted of performing a counterpart test between ROSA/LSTF and PKL facilities, with the main objective of determining the effectiveness of late accident management actions in a small break loss of coolant accident. The results obtained by TRACE code for PKL experiment SBLOCA G7.1 (a scaled model of Konvoi reactor) were in good agreement with the experiments. However, in the simulation process, uncertainty was not accounted. Uncertainty, analysis, following the principles of Best Estimate Plus Uncertainty (BEPU) approach, must be performed to measure the effect of uncertainties on the evolution of safety variables of interest, such as the maximum of the Peak Cladding Temperature (PCTmax) in the experiment. In this paper we present a comparison between two uncertainty analysis techniques. The first technique is based on order statistics that makes use of Wilks' formula. The second technique is based on a Generalized Additive Model (GAM) that substitutes the thermal-hydraulic code, without and with consideration of errors in adjusting the GAM model. The comparison of the uncertainty analysis results makes use of several performance metrics such as coverage, Coefficient of Variation and conservativeness. Based on the results of these metrics it can be concluded that the GAMPE (GAM Plus Error) provides the best performance, in particular, when using small sample size, i.e. n = 59, 93. For larger sample sizes, i.e. n = 124, 153, GAMPE and Wilks' results presents similar performance.This work has been developed partially with the support of Programa de Apoyo a la Investigacion y Desarrollo of UPV (PAID). Authors are grateful to Spanish CSN (Consejo de Seguridad Nuclear) for the financial support of these researches: (Research Project SIN/4078/2013/640; MASA Project) and (Research Project 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 Riunet20172017-01-01journal articlehttp://purl.org/coar/resource_type/c_6501VoRhttp://purl.org/coar/version/c_970fb48d4fbd8a85info:eu-repo/semantics/articleapplication/pdfapplication/pdfhttps://riunet.upv.es/handle/10251/102267reponame:RiuNet. Repositorio Institucional de la Universitat Politécnica de Valénciainstname:Universitat Politècnica de València (UPV)InglésengConsejo de Seguridad Nuclear https://doi.org/10.13039/501100006055 SIN%2F4078%2F2013%2F640open accesshttp://purl.org/coar/access_right/c_abf2Reserva de todos los derechoshttp://rightsstatements.org/vocab/InC/1.0/info:eu-repo/semantics/openAccessoai:riunet.upv.es:10251/1022672026-06-13T07:49:27Z
dc.title.none.fl_str_mv Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
title Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
spellingShingle Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
Sanchez Saez, Francisco|||0000-0002-3011-9884
Uncertainty
PKL
Cladding temperature
TRACE
Wilks
GAM
BEPU
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
title_short Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
title_full Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
title_fullStr Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
title_full_unstemmed Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
title_sort Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods
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 Uncertainty
PKL
Cladding temperature
TRACE
Wilks
GAM
BEPU
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
topic Uncertainty
PKL
Cladding temperature
TRACE
Wilks
GAM
BEPU
ESTADISTICA E INVESTIGACION OPERATIVA
INGENIERIA NUCLEAR
description [EN] The Nuclear Energy Agency auspices simulation of experiments in different facilities under several programs. One on them consisted of performing a counterpart test between ROSA/LSTF and PKL facilities, with the main objective of determining the effectiveness of late accident management actions in a small break loss of coolant accident. The results obtained by TRACE code for PKL experiment SBLOCA G7.1 (a scaled model of Konvoi reactor) were in good agreement with the experiments. However, in the simulation process, uncertainty was not accounted. Uncertainty, analysis, following the principles of Best Estimate Plus Uncertainty (BEPU) approach, must be performed to measure the effect of uncertainties on the evolution of safety variables of interest, such as the maximum of the Peak Cladding Temperature (PCTmax) in the experiment. In this paper we present a comparison between two uncertainty analysis techniques. The first technique is based on order statistics that makes use of Wilks' formula. The second technique is based on a Generalized Additive Model (GAM) that substitutes the thermal-hydraulic code, without and with consideration of errors in adjusting the GAM model. The comparison of the uncertainty analysis results makes use of several performance metrics such as coverage, Coefficient of Variation and conservativeness. Based on the results of these metrics it can be concluded that the GAMPE (GAM Plus Error) provides the best performance, in particular, when using small sample size, i.e. n = 59, 93. For larger sample sizes, i.e. n = 124, 153, GAMPE and Wilks' results presents similar performance.
publishDate 2017
dc.date.none.fl_str_mv 2017
2017-01-01
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/10251/102267
url https://riunet.upv.es/handle/10251/102267
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 https://doi.org/10.13039/501100006055 SIN%2F4078%2F2013%2F640
dc.rights.none.fl_str_mv open access
http://purl.org/coar/access_right/c_abf2
Reserva de todos los derechos
http://rightsstatements.org/vocab/InC/1.0/
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
Reserva de todos los derechos
http://rightsstatements.org/vocab/InC/1.0/
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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