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Verification of the Parallel Pin-Wise Core Simulator pCTF/PARCSv3.2 in Operational Control Rod Drop Transient Scenarios

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Verification of the Parallel Pin-Wise Core Simulator pCTF/PARCSv3.2 in Operational Control Rod Drop Transient Scenarios

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dc.contributor.author Ramos Peinado, Enrique es_ES
dc.contributor.author Roman 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.contributor.author Ortego, Alberto es_ES
dc.contributor.author Posada-Barral, Jose Maria es_ES
dc.date.accessioned 2020-11-17T04:32:49Z
dc.date.available 2020-11-17T04:32:49Z
dc.date.issued 2017 es_ES
dc.identifier.issn 0029-5639 es_ES
dc.identifier.uri http://hdl.handle.net/10251/155130
dc.description.abstract [EN] Thanks to advances in computer technology, it is feasible to obtain detailed reactor core descriptions for safety analysis of the light water reactor (LWR), in order to represent realistically the fuel elements design, as is the case for three-dimensional coupled simulations for local neutron kinetics and thermal hydraulics. This scenario requires an efficient thermal-hydraulic code that can produce a response in a reasonable time for large-scale, detailed models. In two-fluid codes, such as the thermal-hydraulic subchannel code COBRA-TF, the time restriction is even more important, since the set of equations to be solved is more complex. We have developed a message passing interface parallel version of COBRA-TF, called pCTF. The parallel code is based on a cell-oriented domain decomposition approach, and performs well in models that consist of many cells. The Jacobian matrix is computed in parallel, with each processor in charge of calculating the coefficients related to a subset of the cells. Furthermore, the resulting system of linear equations is also solved in parallel, by exploiting solvers and preconditioners from PETSc. The goal of this study is to demonstrate the capability of the recently developed pCTF/PARCS coupled code to simulate large cores with a pin-by-pin level of detail in an acceptable computational time, using for this purpose two control rod drop operational transients that took place in the core of a three-loop pressurized water reactor. As a result, the main safety parameters of the core hot channel have been calculated by the coupled code in a pin level of detail, obtaining best estimate results for this transient. 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 Economia y Competitividad under Projects SLEPc-HS (TIN2016-75985-P) and NUC-MULTPHYS (ENE2012-34585). es_ES
dc.language Inglés es_ES
dc.publisher Taylor & Francis es_ES
dc.relation UPV/PAID-05-12 es_ES
dc.relation UPV/PAID-05-11-2810 es_ES
dc.relation MINECO/TIN2016-75985-P es_ES
dc.relation MINECO/ENE2012-34585 es_ES
dc.relation.ispartof Nuclear Science and Engineering es_ES
dc.rights Reserva de todos los derechos es_ES
dc.subject Subchannel simulation es_ES
dc.subject Parallel computing es_ES
dc.subject COBRA-TF es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.subject.classification CIENCIAS DE LA COMPUTACION E INTELIGENCIA ARTIFICIAL es_ES
dc.title Verification of the Parallel Pin-Wise Core Simulator pCTF/PARCSv3.2 in Operational Control Rod Drop Transient Scenarios es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1080/00295639.2017.1320892 es_ES
dc.rights.accessRights Cerrado es_ES
dc.contributor.affiliation Universitat Politècnica de València. Departamento de Sistemas Informáticos y Computación - Departament de Sistemes Informàtics i Computació 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 Ramos Peinado, E.; Roman Moltó, JE.; Abarca Giménez, A.; Miró Herrero, R.; Bermejo, JA.; Ortego, A.; Posada-Barral, JM. (2017). Verification of the Parallel Pin-Wise Core Simulator pCTF/PARCSv3.2 in Operational Control Rod Drop Transient Scenarios. Nuclear Science and Engineering. 187(3):254-267. https://doi.org/10.1080/00295639.2017.1320892 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion https://doi.org/10.1080/00295639.2017.1320892 es_ES
dc.description.upvformatpinicio 254 es_ES
dc.description.upvformatpfin 267 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 187 es_ES
dc.description.issue 3 es_ES
dc.relation.pasarela S\351348 es_ES
dc.contributor.funder Universitat Politècnica de València es_ES
dc.contributor.funder Ministerio de Economía y Competitividad es_ES


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