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

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

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dc.contributor.author Sanchez-Saez, Francisco es_ES
dc.contributor.author Carlos Alberola, Sofía es_ES
dc.contributor.author Villanueva López, José Felipe es_ES
dc.contributor.author Sánchez Galdón, Ana Isabel es_ES
dc.contributor.author Martorell Alsina, Sebastián Salvador es_ES
dc.date.accessioned 2023-06-07T18:01:22Z
dc.date.available 2023-06-07T18:01:22Z
dc.date.issued 2020-06 es_ES
dc.identifier.issn 0149-1970 es_ES
dc.identifier.uri http://hdl.handle.net/10251/193943
dc.description.abstract [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. es_ES
dc.description.sponsorship 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). es_ES
dc.language Inglés es_ES
dc.publisher Elsevier es_ES
dc.relation.ispartof Progress in Nuclear Energy es_ES
dc.rights Reconocimiento - No comercial - Sin obra derivada (by-nc-nd) es_ES
dc.subject Spent fuel pool es_ES
dc.subject TRACE es_ES
dc.subject Elastic Net es_ES
dc.subject LASSO regression es_ES
dc.subject Uncertainty analysis es_ES
dc.subject Wilks es_ES
dc.subject.classification ESTADISTICA E INVESTIGACION OPERATIVA es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1016/j.pnucene.2020.103345 es_ES
dc.relation.projectID info:eu-repo/grantAgreement/CONSEJO DE SEGURIDAD NUCLEAR//STN%2F4524%2F2015%2F640//ACUERDO ESPECIFICO DE COLABORACION CSN-UPV-UPC-UPM CAMP ESPAÑA/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/CONSEJO DE SEGURIDAD NUCLEAR//MASA-2//METODOS AVANZADOS DE SIMULACION Y ANALISIS EN EL CAMPO DE LA SEGURIDAD NUCLEAR, SEGUNDA PARTE/ es_ES
dc.rights.accessRights Abierto es_ES
dc.contributor.affiliation Universitat Politècnica de València. Escuela Técnica Superior de Ingenieros Industriales - Escola Tècnica Superior d'Enginyers Industrials es_ES
dc.description.bibliographicCitation Sanchez-Saez, F.; Carlos Alberola, S.; Villanueva López, JF.; Sánchez Galdón, AI.; Martorell Alsina, SS. (2020). Uncertainty analysis of a loss of cooling and loss of coolant accident in a spent fuel pool using TRACE. Progress in Nuclear Energy. 124:1-8. https://doi.org/10.1016/j.pnucene.2020.103345 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion https://doi.org/10.1016/j.pnucene.2020.103345 es_ES
dc.description.upvformatpinicio 1 es_ES
dc.description.upvformatpfin 8 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 124 es_ES
dc.relation.pasarela S\421025 es_ES
dc.contributor.funder CONSEJO DE SEGURIDAD NUCLEAR es_ES
dc.subject.ods 07.- Asegurar el acceso a energías asequibles, fiables, sostenibles y modernas para todos es_ES


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