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dc.contributor.author | Bernal-Garcia, Alvaro | es_ES |
dc.contributor.author | Roman, Jose E. | es_ES |
dc.contributor.author | Miró Herrero, Rafael | es_ES |
dc.contributor.author | Verdú Martín, Gumersindo Jesús | es_ES |
dc.date.accessioned | 2020-01-30T21:02:00Z | |
dc.date.available | 2020-01-30T21:02:00Z | |
dc.date.issued | 2018 | es_ES |
dc.identifier.issn | 0149-1970 | es_ES |
dc.identifier.uri | http://hdl.handle.net/10251/136098 | |
dc.description.abstract | [EN] The spatial distribution of the neutron flux within the core of nuclear reactors is a key factor in nuclear safety. The easiest and fastest way to determine it is by solving the eigenvalue problem of the neutron diffusion equation, which only contains spatial derivatives. The approximation of these derivatives is performed by discretizing the geometry and using numerical methods. In this work, the authors used a finite volume method based on a polynomial expansion of the neutron flux. Once these terms are discretized, a set of matrix equations is obtained, which constitutes the eigenvalue problem. A very effective class of methods for the solution of eigenvalue problems are those based on projection onto a low-dimensional subspace, such as Krylov subspaces. Thus, the SLEPc library was used for solving the eigenvalue problem by means of the Krylov-Schur method, which also uses projection methods of PETSc for solving linear systems. This work includes a complete sensitivity analysis of different issues: mesh, polynomial terms, linear systems solvers and parallelization. | es_ES |
dc.description.sponsorship | This work has been partially supported by the Spanish Ministerio de Eduacion Cultura y Deporte under the grant FPU13/01009, the Spanish Ministerio de Ciencia e Innovacion under the project ENE2014-59442-P, the Spanish Ministerio de Economia y Competitividad and the European Fondo Europeo de Desarrollo Regional (FEDER) under the project ENE2015-68353-P (MINECO/FEDER), the Generalitat Valenciana under the project PROMETEOII/2014/008, and the Spanish Ministerio de Economia y Competitividad and the European Fondo Europeo de Desarrollo Regional (FEDER) under the project TIN2016-075985-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 | Eigenvalue problem | es_ES |
dc.subject | Neutron diffusion equation | es_ES |
dc.subject | Finite volume method | es_ES |
dc.subject | Krylov subspaces | es_ES |
dc.subject.classification | INGENIERIA NUCLEAR | es_ES |
dc.subject.classification | CIENCIAS DE LA COMPUTACION E INTELIGENCIA ARTIFICIAL | es_ES |
dc.title | Calculation of multiple eigenvalues of the neutron diffusion equation discretized with a parallelized finite volume method | es_ES |
dc.type | Artículo | es_ES |
dc.identifier.doi | 10.1016/j.pnucene.2018.02.006 | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/GVA//PROMETEOII%2F2014%2F008/ES/New improved capacities in 3d-VALKIN (Valencian Neutronic Kinetisc). N3D-VALKIN/ | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/MINECO//ENE2014-59442-P/ES/DESARROLLO DE NUEVOS MODELOS Y CAPACIDADES EN EL SISTEMA DE CODIGOS ACOPLADO VALKIN%2FTH-3D. VERIFICACION, VALIDACION Y CUANTIFICACION DE INCERTIDUMBRES/ | 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/MINECO//TIN2016-75985-P/ES/SOLVERS DE VALORES PROPIOS ALTAMENTE ESCALABLES EN EL CONTEXTO DE LA BIBLIOTECA SLEPC/ | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/MECD//FPU13%2F01009/ES/FPU13%2F01009/ | es_ES |
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 Sistemas Informáticos y Computación - Departament de Sistemes Informàtics i Computació | es_ES |
dc.description.bibliographicCitation | Bernal-Garcia, A.; Roman, JE.; Miró Herrero, R.; Verdú Martín, GJ. (2018). Calculation of multiple eigenvalues of the neutron diffusion equation discretized with a parallelized finite volume method. Progress in Nuclear Energy. 105:271-278. https://doi.org/10.1016/j.pnucene.2018.02.006 | es_ES |
dc.description.accrualMethod | S | es_ES |
dc.relation.publisherversion | https://doi.org/10.1016/j.pnucene.2018.02.006 | es_ES |
dc.description.upvformatpinicio | 271 | es_ES |
dc.description.upvformatpfin | 278 | es_ES |
dc.type.version | info:eu-repo/semantics/publishedVersion | es_ES |
dc.description.volume | 105 | es_ES |
dc.relation.pasarela | S\373621 | es_ES |
dc.contributor.funder | Generalitat Valenciana | es_ES |
dc.contributor.funder | Ministerio de Economía y Competitividad | es_ES |
dc.contributor.funder | Ministerio de Educación, Cultura y Deporte | es_ES |