Mostrar el registro sencillo del ítem
dc.contributor.author | Ánchel Añó, Francisco Constantino | es_ES |
dc.contributor.author | Barrachina Celda, Teresa María | es_ES |
dc.contributor.author | Miró Herrero, Rafael | es_ES |
dc.contributor.author | Verdú Martín, Gumersindo Jesús | es_ES |
dc.contributor.author | Juanas ., J. | es_ES |
dc.contributor.author | Macián-Juan, R. | es_ES |
dc.date.accessioned | 2014-05-06T18:23:21Z | |
dc.date.issued | 2012-05 | |
dc.identifier.issn | 0029-5493 | |
dc.identifier.uri | http://hdl.handle.net/10251/37264 | |
dc.description.abstract | The Best Estimate analysis consists of a coupled thermal-hydraulic and neutronic description of the nuclear system's behavior; uncertainties from both aspects should be included and jointly propagated. This paper presents a study of the influence of the uncertainty in the macroscopic neutronic information that describes a three-dimensional core model on the most relevant results of the simulation of a Reactivity Induced Accident (RIA). The analyses of a BWR-RIA and a PWR-RIA have been carried out with a three-dimensional thermal-hydraulic and neutronic model for the coupled system TRACE-PARCS and RELAP-PARCS. The cross section information has been generated by the SIMTAB methodology based on the joint use of CASMO-SIMULATE. The statistically based methodology performs a Monte-Carlo kind of sampling of the uncertainty in the macroscopic cross sections. The size of the sampling is determined by the characteristics of the tolerance intervals by applying the Noether¿Wilks formulas. A number of simulations equal to the sample size have been carried out in which the cross sections used by PARCS are directly modified with uncertainty, and non-parametric statistical methods are applied to the resulting sample of the values of the output variables to determine their intervals of tolerance. | es_ES |
dc.format.extent | 9 | es_ES |
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.classification | ESTADISTICA E INVESTIGACION OPERATIVA | es_ES |
dc.subject.classification | INGENIERIA NUCLEAR | es_ES |
dc.title | Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic-neutronic simulations | es_ES |
dc.type | Artículo | es_ES |
dc.embargo.lift | 10000-01-01 | |
dc.embargo.terms | forever | es_ES |
dc.identifier.doi | 10.1016/j.nucengdes.2011.11.016 | |
dc.rights.accessRights | Cerrado | 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.contributor.affiliation | Universitat Politècnica de València. Departamento de Ingeniería Química y Nuclear - Departament d'Enginyeria Química i Nuclear | es_ES |
dc.description.bibliographicCitation | Ánchel Añó, FC.; Barrachina Celda, TM.; Miró Herrero, R.; Verdú Martín, GJ.; Juanas ., J.; Macián-Juan, R. (2012). Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic-neutronic simulations. Nuclear Engineering and Design. 246:98-106. doi:10.1016/j.nucengdes.2011.11.016 | es_ES |
dc.description.accrualMethod | S | es_ES |
dc.relation.conferencename | International Conference Nuclear Energy for New Europe | es_ES |
dc.relation.conferencedate | September 6-9, 2010 | es_ES |
dc.relation.conferenceplace | Portoro, Slovenia | es_ES |
dc.relation.publisherversion | http://dx.doi.org/10.1016/j.nucengdes.2011.11.016 | es_ES |
dc.description.upvformatpinicio | 98 | es_ES |
dc.description.upvformatpfin | 106 | es_ES |
dc.type.version | info:eu-repo/semantics/publishedVersion | es_ES |
dc.description.volume | 246 | es_ES |
dc.relation.senia | 239249 |