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CFD-Neutronic coupled calculation of a PWR fuel assembly considering pressure drop and turbulence produced by spacer grids.

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CFD-Neutronic coupled calculation of a PWR fuel assembly considering pressure drop and turbulence produced by spacer grids.

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dc.contributor.author Peña-Monferrer, Carlos es_ES
dc.contributor.author Pellacani, F. es_ES
dc.contributor.author Chiva Vicent, Sergio es_ES
dc.contributor.author Barrachina Celda, Teresa María es_ES
dc.contributor.author Miró Herrero, Rafael es_ES
dc.contributor.author Macián-Juan, R. es_ES
dc.date.accessioned 2015-03-27T18:05:39Z
dc.date.issued 2012
dc.identifier.issn 1137-2885
dc.identifier.uri http://hdl.handle.net/10251/48423
dc.description.abstract [EN] A computational code system called Coupled Solver ANSYS CFX/PARCS (CSAP) based on coupling the 3D neutron diffusion code PARCS v2.7 and the ANSYS CFX 13.0 Computational Fluid Dynamics (CFD) code has been developed as a tool for nuclear reactor systems simulations. This paper presents the coupling methodology between the CFD and the neutronic code. The methodology to simulate a 3D-neutronic problem coupled with 1D thermalhydraulics is already a mature technology, being part of the regular calculations performed to analyze different kinds of Reactivity Insertion Accidents (RIA) and asymmetric transients in Nuclear Power Plants, with state-of-the-art coupled codes like TRAC-B/NEM, RELAP5/PARCS, TRACE/PARCS, RELAP3D, RETRAN3D, etc. The transport of neutrons depends on several parameters, like fuel temperature, moderator temperature and density, boron concentration and fuel rod insertion. These data are calculated by the CFD code with high local resolution and used as input to the neutronic code to calculate a 3D nodal power distribution that will be returned and remapped to the CFD code control volumes (cells). Since two different nodalizations are used to discretize the same system, an averaging and interpolating procedure is needed to realize an effective data exchange. These procedures have been developed by means of the ANSYS CFX “User Fortran” interface; a library with several subroutines has been developed for calculation and synchronization purposes. The data exchange is realized by means of the Parallel Virtual Machine (PVM) software package. In this contribution, steady-state and transient results of a quarter of PWR fuel assembly with cold water injection are presented and compared with obtained results from a RELAP5/PARCS v2.7 coupled calculation. A simplified model for the spacers has been included. A methodology has been introduced to take into account the pressure drop and the turbulence enhancement produced by the spacers. es_ES
dc.description.sponsorship This research was supported by the “Plan Nacional de I+D+i” Project EXPERTISER ENE2010-21368-C02-01 and ENE2010-21368-C02-02.
dc.language Inglés es_ES
dc.publisher Sne es_ES
dc.relation MICINN/ENE2010- 21368-C02-01 es_ES
dc.relation MICINN/ENE2010-21368-C02-02
dc.relation.ispartof Nuclear Espana es_ES
dc.rights Reserva de todos los derechos es_ES
dc.subject CFX es_ES
dc.subject PARCS es_ES
dc.subject RELAP es_ES
dc.subject Coupling es_ES
dc.subject TH/N es_ES
dc.subject CSAP es_ES
dc.subject.classification ESTADISTICA E INVESTIGACION OPERATIVA es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title CFD-Neutronic coupled calculation of a PWR fuel assembly considering pressure drop and turbulence produced by spacer grids. es_ES
dc.type Artículo es_ES
dc.type Comunicación en congreso
dc.embargo.lift 10000-01-01
dc.embargo.terms forever es_ES
dc.rights.accessRights Abierto es_ES
dc.contributor.affiliation Universitat Politècnica de València. Instituto de Ingeniería Energética - Institut d'Enginyeria Energètica 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 Peña-Monferrer, C.; Pellacani, F.; Chiva Vicent, S.; Barrachina Celda, TM.; Miró Herrero, R.; Macián-Juan, R. (2012). CFD-NEUTRONIC COUPLED CALCULATION OF A PWR FUEL ASSEMBLY CONSIDERING PRESSURE DROP AND TURBULENCE PRODUCED BY SPACER GRIDS. Nuclear Espana. 52-61. http://hdl.handle.net/10251/48423 es_ES
dc.description.accrualMethod Senia es_ES
dc.relation.conferencename 38 Reunión Anual de la Sociedad Nuclear Española
dc.relation.conferencedate October 17-19, 2012
dc.relation.conferenceplace Cáceres, Spain
dc.description.upvformatpinicio 52 es_ES
dc.description.upvformatpfin 61 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.relation.senia 241321
dc.contributor.funder Minsiterio de Ciencia e Innovación


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