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Adaptive time-step control for modal methods to integrate the neutron diffusion equation

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Adaptive time-step control for modal methods to integrate the neutron diffusion equation

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dc.contributor.author Carreño, Amanda es_ES
dc.contributor.author Vidal-Ferràndiz, Antoni es_ES
dc.contributor.author Ginestar Peiro, Damián es_ES
dc.contributor.author Verdú Martín, Gumersindo Jesús es_ES
dc.date.accessioned 2022-04-27T10:07:19Z
dc.date.available 2022-04-27T10:07:19Z
dc.date.issued 2021-02 es_ES
dc.identifier.issn 1738-5733 es_ES
dc.identifier.uri http://hdl.handle.net/10251/182189
dc.description.abstract [EN] The solution of the time-dependent neutron diffusion equation can be approximated using quasi-static methods that factorise the neutronic flux as the product of a time dependent function times a shape function that depends both on space and time. A generalization of this technique is the updated modal method. This strategy assumes that the neutron flux can be decomposed into a sum of amplitudes multiplied by some shape functions. These functions, known as modes, come from the solution of the eigenvalue problems associated with the static neutron diffusion equation that are being updated along the transient. In previous works, the time step used to update the modes is set to a fixed value and this implies the need of using small time-steps to obtain accurate results and, consequently, a high computational cost. In this work, we propose the use of an adaptive control time-step that reduces automatically the time-step when the algorithm detects large errors and increases this value when it is not necessary to use small steps. Several strategies to compute the modes updating time step are proposed and their performance is tested for different transients in benchmark reactors with rectangular and hexagonal geometry. es_ES
dc.description.sponsorship This work has been partially supported by Spanish Ministerio de Economia y Competitividad under projects ENE2017-89029-P and MTM2017-85669-P and financed with the help of a Primeros Proyectos de Investigacion (PAID-06-18) from Vicerrectorado de Investigacion, Innovacion y Transferencia of the Universitat Politecnica de Valencia. es_ES
dc.language Inglés es_ES
dc.publisher Elsevier es_ES
dc.relation.ispartof Nuclear Engineering and Technology es_ES
dc.rights Reconocimiento - No comercial - Sin obra derivada (by-nc-nd) es_ES
dc.subject Adaptive Time-Step es_ES
dc.subject Modal Method es_ES
dc.subject Finite Element Method es_ES
dc.subject Time Dependent Neutron Diffusion Equation es_ES
dc.subject.classification MATEMATICA APLICADA es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Adaptive time-step control for modal methods to integrate the neutron diffusion equation es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1016/j.net.2020.07.004 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/UPV//PAID-06-18/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/AEI/Plan Estatal de Investigación Científica y Técnica y de Innovación 2013-2016/MTM2017-85669-P/ES/PROBLEMAS MATRICIALES: COMPUTACION, TEORIA Y APLICACIONES/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/UPV-VIN//SP20180095//Aproximaciones de alto orden para la ecuación del transporte neutrónico/ 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 Matemática Aplicada - Departament de Matemàtica Aplicada es_ES
dc.description.bibliographicCitation Carreño, A.; Vidal-Ferràndiz, A.; Ginestar Peiro, D.; Verdú Martín, GJ. (2021). Adaptive time-step control for modal methods to integrate the neutron diffusion equation. Nuclear Engineering and Technology. 53(2):399-413. https://doi.org/10.1016/j.net.2020.07.004 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion https://doi.org/10.1016/j.net.2020.07.004 es_ES
dc.description.upvformatpinicio 399 es_ES
dc.description.upvformatpfin 413 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 53 es_ES
dc.description.issue 2 es_ES
dc.relation.pasarela S\417217 es_ES
dc.contributor.funder AGENCIA ESTATAL DE INVESTIGACION es_ES
dc.contributor.funder UNIVERSIDAD POLITECNICA DE VALENCIA es_ES
dc.contributor.funder Universitat Politècnica de València es_ES


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