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Uncertainty analysis of a large break loss of coolant accident in a pressurized water reactor using non-parametric methods

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Uncertainty analysis of a large break loss of coolant accident in a pressurized water reactor using non-parametric methods

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dc.contributor.author Sanchez Saez, Francisco es_ES
dc.contributor.author Sánchez Galdón, Ana Isabel es_ES
dc.contributor.author Villanueva López, José Felipe es_ES
dc.contributor.author Carlos Alberola, Sofía es_ES
dc.contributor.author Martorell Alsina, Sebastián Salvador es_ES
dc.date.accessioned 2019-06-07T20:06:04Z
dc.date.available 2019-06-07T20:06:04Z
dc.date.issued 2018 es_ES
dc.identifier.issn 0951-8320 es_ES
dc.identifier.uri http://hdl.handle.net/10251/121779
dc.description.abstract [DE] The safety analysis of nuclear power plant is moving toward a realistic approach in which the simulations performed using best estimate computer codes must be accompanied by an uncertainty analysis, known as the Best Estimate Plus Uncertainties approach. The most popular statistical method used in these analyses is the Wilts' method, which is based on the principle of order statistics for determining a certain coverage of the Figures of-Merit with an appropriate degree of confidence. However, there exist other statistical techniques that could provide similar or even better results. This paper explores the performance of alternative non-parametric methods as compared to the Wilks' method of obtaining such Figure-of-Merits tolerance intervals. Three methods are investigated, i.e. Hutson and Beran-Hall methods and a bootstrap method. All the techniques have been used to perform the uncertainty analysis of a Large-Break Loss of Coolant Accident. The Figure-of-Merit of interest in this application is the maximum value reached by the Peaking Clad Temperature. In order to analyze the results obtained by the different methods, four performance metrics are proposed to measure the coverage, dispersion, conservativeness, and robustness of the tolerance intervals. (C) 2018 Elsevier Ltd. All rights reserved. es_ES
dc.description.sponsorship The authors are also grateful to the Spanish Consejo de Seguridad Nuclear for the financial support they provided for Research ProjectsSIN/4078/2013/640 (MASA Project) and STN/4524/2015/640 (CAMP Project). es_ES
dc.language Inglés es_ES
dc.publisher Elsevier es_ES
dc.relation.ispartof Reliability Engineering & System Safety es_ES
dc.rights Reconocimiento - No comercial - Sin obra derivada (by-nc-nd) es_ES
dc.subject Uncertainty es_ES
dc.subject Best-estimate plus uncertainty es_ES
dc.subject Deterministic safety analysis es_ES
dc.subject Large break loss of coolant accident es_ES
dc.subject Wilks method es_ES
dc.subject Order statistics es_ES
dc.subject Non-parametric methods es_ES
dc.subject.classification ESTADISTICA E INVESTIGACION OPERATIVA es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Uncertainty analysis of a large break loss of coolant accident in a pressurized water reactor using non-parametric methods es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1016/j.ress.2018.02.005 es_ES
dc.relation.projectID info:eu-repo/grantAgreement/CSN//SIN%2F4078%2F2013%2F640/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/CSN//STN%2F4524%2F2015%2F640/
dc.rights.accessRights Abierto 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 Sanchez Saez, F.; Sánchez Galdón, AI.; Villanueva López, JF.; Carlos Alberola, S.; Martorell Alsina, SS. (2018). Uncertainty analysis of a large break loss of coolant accident in a pressurized water reactor using non-parametric methods. Reliability Engineering & System Safety. 174:19-28. https://doi.org/10.1016/j.ress.2018.02.005 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion https://doi.org/10.1016/j.ress.2018.02.005 es_ES
dc.description.upvformatpinicio 19 es_ES
dc.description.upvformatpfin 28 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 174 es_ES
dc.relation.pasarela S\355481 es_ES
dc.contributor.funder Consejo de Seguridad Nuclear es_ES


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