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dc.contributor.author | Mesado, C. | es_ES |
dc.contributor.author | Miró Herrero, Rafael | es_ES |
dc.contributor.author | Verdú Martín, Gumersindo Jesús | es_ES |
dc.date.accessioned | 2021-04-28T03:32:28Z | |
dc.date.available | 2021-04-28T03:32:28Z | |
dc.date.issued | 2020 | es_ES |
dc.identifier.issn | 0149-1970 | es_ES |
dc.identifier.uri | http://hdl.handle.net/10251/165730 | |
dc.description.abstract | [EN] This work covers an important point of the benchmark released by the expert group on Uncertainty Analysis in Modeling of Light Water Reactors (UAM-LWR). This ambitious benchmark aims to determine the uncertainty in LWR systems and processes in all stages of calculation, with emphasis on multi-physics (coupled) and multi-scale simulations. Specifically, in this work, a simplified BWR core is used to propagate the uncertainty of nuclear data. Due to a high computational cost in the analysis all fuel assemblies are modeled as fresh. The propagation is subdivided into two levels i) assembly level ¿with SCALE6.2.1 and SAMPLER module¿, and ii) core level, ¿with PARCSv3.2 and DAKOTA 6.3¿. The first level takes into account the uncertainties contained in the master library ENDF/B-VII.1 and as a result a problem-dependent neutronic library in NEMTAB format is obtained using TXT2NTAB code. This is a friendly Matlab code developed within this work. Finally, the uncertainty contained in the neutronic library is further propagated through PARCS. A different approach is presented in this work to propagate the uncertainty between codes. Following this approach only two neutronic libraries are generated, one with the average responses and the other with their standard deviations. Then, the standard deviation and a matrix of perturbation factors are used to perturb the main neutronic parameters. A parallel work is done to propagate the thermal-hydraulic parameters in a PWR core. | es_ES |
dc.description.sponsorship | The authors of this work thank IBERINCO (Iberdrola Ingenieria y Construcci.on, S. A.) for the shared data which made possible the validation of the lattice physics model. Moreover, this work was possible thanks to the UAM-LWR benchmark release, thanks to its organizers who requested the development of TXT2NTAB Matlab program. Finally, the authors sincerely thank to the Ministerio de Economia, Industria y Competitividad, Spain and the "Plan Nacional de IthornDthorni" for funding the projects NUC-MULTPHYS ENE2012-34585 and ENE2017-89029-P. | es_ES |
dc.language | Inglés | es_ES |
dc.publisher | Elsevier | es_ES |
dc.relation.ispartof | Progress in Nuclear Energy | es_ES |
dc.rights | Reserva de todos los derechos | es_ES |
dc.subject | U&S analysis | es_ES |
dc.subject | Uncertainty propagation | es_ES |
dc.subject | 3D core model | es_ES |
dc.subject | SCALE6.2 | es_ES |
dc.subject | SAMPLER | es_ES |
dc.subject | PARCS | es_ES |
dc.subject | TXT2NTAB | es_ES |
dc.subject.classification | INGENIERIA NUCLEAR | es_ES |
dc.title | Methodology for neutronic uncertainty propagation and application to a UAM-LWR benchmark | es_ES |
dc.type | Artículo | es_ES |
dc.identifier.doi | 10.1016/j.pnucene.2020.103389 | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/MINECO//ENE2012-34585/ES/Desarrollo de una plataforma multifísica de altas prestaciones para simulaciones Termohidráulico-Neutrónicas en ingeniería nuclear/ | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/MINECO//ENE2015-68353-P/ES/DESARROLLO DE UN CODIGO DE TRANSPORTE NEUTRONICO MODAL 3D POR EL METODO DE LOS VOLUMENES FINITOS Y ORDENADAS DISCRETAS/ | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/AEI/Plan Estatal de Investigación Científica y Técnica y de Innovación 2013-2016/ENE2017-89029-P/ES/VERIFICACION, VALIDACION CUANTIFICACION DE INCERTIDUMBRES Y MEJORA DE LA PLATAFORMA NEUTRONICA%2FTERMOHIDRAULICA PANTHER/ | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/AEI/Plan Estatal de Investigación Científica y Técnica y de Innovación 2017-2020/PGC2018-096437-B-I00/ES/APLICACION INTEGRADA DE FISICA DE REACTORES PARA SIMULACIONES A GRAN ESCALA/ | es_ES |
dc.rights.accessRights | Abierto | es_ES |
dc.contributor.affiliation | Universitat Politècnica de València. Instituto de Seguridad Industrial, Radiofísica y Medioambiental - Institut de Seguretat Industrial, Radiofísica i Mediambiental | 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 | Mesado, C.; Miró Herrero, R.; Verdú Martín, GJ. (2020). Methodology for neutronic uncertainty propagation and application to a UAM-LWR benchmark. Progress in Nuclear Energy. 126:1-12. https://doi.org/10.1016/j.pnucene.2020.103389 | es_ES |
dc.description.accrualMethod | S | es_ES |
dc.relation.publisherversion | https://doi.org/10.1016/j.pnucene.2020.103389 | es_ES |
dc.description.upvformatpinicio | 1 | es_ES |
dc.description.upvformatpfin | 12 | es_ES |
dc.type.version | info:eu-repo/semantics/publishedVersion | es_ES |
dc.description.volume | 126 | es_ES |
dc.relation.pasarela | S\431539 | es_ES |
dc.contributor.funder | Agencia Estatal de Investigación | es_ES |
dc.contributor.funder | Ministerio de Economía y Competitividad | es_ES |
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