- -

Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2.7

RiuNet: Repositorio Institucional de la Universidad Politécnica de Valencia

Compartir/Enviar a

Citas

Estadísticas

  • Estadisticas de Uso

Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2.7

Mostrar el registro sencillo del ítem

Ficheros en el ítem

Thumbnail
Nombre: pcobra.pdf
Tamaño: 885.5Kb
Formato: PDF
Descripción: Versión del Autor.
Abrir
[Cerrado]
Nombre: ane-pctf.pdf
Tamaño: 3.601Mb
Formato: PDF
Descripción: Versión editorial
Solicitar una copia al autor
dc.contributor.author Ramos Peinado, Enrique es_ES
dc.contributor.author Román Moltó, José Enrique es_ES
dc.contributor.author Abarca Giménez, Agustín es_ES
dc.contributor.author Miró Herrero, Rafael es_ES
dc.contributor.author Bermejo, Juan A. es_ES
dc.date.accessioned 2017-05-17T08:06:04Z
dc.date.available 2017-05-17T08:06:04Z
dc.date.issued 2016-01
dc.identifier.issn 0306-4549
dc.identifier.uri http://hdl.handle.net/10251/81251
dc.description This is the author’s version of a work that was accepted for publication in Annals of Nuclear Energy. Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. Changes may have been made to this work since it was submitted for publication. A definitive version was subsequently published in Annals of Nuclear Energy, vol. 87, (2016) DOI 10.1016/j.anucene.2015.09.016. es_ES
dc.description.abstract In order to reduce the response time when simulating large reactors in detail, a parallel version of the thermal–hydraulic subchannel code COBRA-TF (CTF) has been developed using the standard Message Passing Interface (MPI). The parallelization is oriented to reactor cells, so it is best suited for models consisting of many cells. The generation of the Jacobian matrix is parallelized, in such a way that each processor is in charge of generating the data associated with a subset of cells. Also, the solution of the linear system of equations is done in parallel, using the PETSc toolkit. With the goal of creating a powerful tool to simulate the reactor core behavior during asymmetrical transients, the 3D neutron diffusion code PARCSv2.7 (PARCS) has been coupled with the parallel version of CTF (pCTF) using the Parallel Virtual Machine (PVM) technology. In order to validate the correctness of the parallel coupled code, a control rod drop transient has been simulated comparing the results with the real experimental measures acquired during an NPP real test. 2015 Elsevier Ltd. All rights reserved. es_ES
dc.description.sponsorship This work has been partially supported by the Universitat Politecnica de Valencia under Projects COBRA_PAR (PAID-05-11-2810) and OpenNUC (PAID-05-12), and by the Spanish Ministerio de Economa y Competitividad under Projects SLEPc-PFE (TIN2013-41049-P) and NUC-MULTPHYS (ENE2012-34585). The authors would like to acknowledge the technical support provided by CNAT and IBERDROLA GENERACION S.A. for the realization of this work. en_EN
dc.language Inglés es_ES
dc.publisher Elsevier es_ES
dc.relation.ispartof Annals of Nuclear Energy es_ES
dc.rights Reserva de todos los derechos es_ES
dc.subject Sub-channel simulation es_ES
dc.subject Parallel computing es_ES
dc.subject PETSc es_ES
dc.subject COBRA-TF es_ES
dc.subject PARCSv2.7 es_ES
dc.subject.classification CIENCIAS DE LA COMPUTACION E INTELIGENCIA ARTIFICIAL es_ES
dc.subject.classification LENGUAJES Y SISTEMAS INFORMATICOS es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2.7 es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1016/j.anucene.2015.09.016
dc.relation.projectID info:eu-repo/grantAgreement/UPV//PAID-05-12/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/UPV//PAID-05-11-2810/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/MINECO//TIN2013-41049-P/ES/EXTENSION DE LA LIBRERIA SLEPC PARA POLINOMIOS MATRICIALES, FUNCIONES MATRICIALES Y ECUACIONES MATRICIALES EN PLATAFORMAS DE COMPUTACION EMERGENTES/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/MINECO//ENE2012-34585/ES/DESARROLLO DE UNA PLATAFORMA MULTIFÍSICAS DE ALTAS PRESTACIONES PARA SIMULACIONES TERMOHIDRAULICO-NEUTRÓNICAS EN INGENIERIA NUCLEAR/ es_ES
dc.rights.accessRights Abierto es_ES
dc.contributor.affiliation Universitat Politècnica de València. Escuela Técnica Superior de Ingenieros Industriales - Escola Tècnica Superior d'Enginyers Industrials es_ES
dc.contributor.affiliation Universitat Politècnica de València. Escola Tècnica Superior d'Enginyeria Informàtica 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.description.bibliographicCitation Ramos Peinado, E.; Román Moltó, JE.; Abarca Giménez, A.; Miró Herrero, R.; Bermejo, JA. (2016). Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2.7. Annals of Nuclear Energy. 87(2):308-317. https://doi.org/10.1016/j.anucene.2015.09.016 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion http://dx.doi.org/10.1016/j.anucene.2015.09.016 es_ES
dc.description.upvformatpinicio 308 es_ES
dc.description.upvformatpfin 317 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 87 es_ES
dc.description.issue 2 es_ES
dc.relation.senia 293639 es_ES
dc.contributor.funder Ministerio de Economía y Competitividad es_ES
dc.contributor.funder Universitat Politècnica de València es_ES


Este ítem aparece en la(s) siguiente(s) colección(ones)

Mostrar el registro sencillo del ítem