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dc.contributor.author | Sánchez Sáez, 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 | 2018-05-19T04:26:36Z | |
dc.date.available | 2018-05-19T04:26:36Z | |
dc.date.issued | 2017 | es_ES |
dc.identifier.issn | 0029-5493 | es_ES |
dc.identifier.uri | http://hdl.handle.net/10251/102267 | |
dc.description.abstract | [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. | es_ES |
dc.description.sponsorship | 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). | en_EN |
dc.language | Inglés | es_ES |
dc.publisher | Elsevier | es_ES |
dc.relation.ispartof | Nuclear Engineering and Design | es_ES |
dc.rights | Reserva de todos los derechos | es_ES |
dc.subject | Uncertainty | es_ES |
dc.subject | PKL | es_ES |
dc.subject | Cladding temperature | es_ES |
dc.subject | TRACE | es_ES |
dc.subject | Wilks | es_ES |
dc.subject | GAM | es_ES |
dc.subject | BEPU | es_ES |
dc.subject.classification | ESTADISTICA E INVESTIGACION OPERATIVA | es_ES |
dc.subject.classification | INGENIERIA NUCLEAR | es_ES |
dc.title | Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods | es_ES |
dc.type | Artículo | es_ES |
dc.identifier.doi | 10.1016/j.nucengdes.2017.04.037 | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/CSN//SIN%2F4078%2F2013%2F640/ | es_ES |
dc.rights.accessRights | Abierto | es_ES |
dc.date.embargoEndDate | 2019-08-01 | es_ES |
dc.contributor.affiliation | Universitat Politècnica de València. Departamento de Ingeniería Química y Nuclear - Departament d'Enginyeria Química i Nuclear | es_ES |
dc.contributor.affiliation | Universitat Politècnica de València. Departamento de Estadística e Investigación Operativa Aplicadas y Calidad - Departament d'Estadística i Investigació Operativa Aplicades i Qualitat | es_ES |
dc.description.bibliographicCitation | Sánchez Sáez, F.; Carlos Alberola, S.; Villanueva López, JF.; Sánchez Galdón, AI.; Martorell Alsina, SS. (2017). Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods. Nuclear Engineering and Design. 319:61-72. https://doi.org/10.1016/j.nucengdes.2017.04.037 | es_ES |
dc.description.accrualMethod | S | es_ES |
dc.relation.publisherversion | https://doi.org/10.1016/j.nucengdes.2017.04.037 | es_ES |
dc.description.upvformatpinicio | 61 | es_ES |
dc.description.upvformatpfin | 72 | es_ES |
dc.type.version | info:eu-repo/semantics/publishedVersion | es_ES |
dc.description.volume | 319 | es_ES |
dc.relation.pasarela | S\337280 | es_ES |
dc.contributor.funder | Consejo de Seguridad Nuclear | es_ES |