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Assembly Discontinuity Factors for the Neutron Diffusion Equation discretized with the Finite Volume Method. Application to BWR

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Assembly Discontinuity Factors for the Neutron Diffusion Equation discretized with the Finite Volume Method. Application to BWR

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Bernal-Garcia, A.; Román Moltó, JE.; Miró Herrero, R.; Verdú Martín, GJ. (2016). Assembly Discontinuity Factors for the Neutron Diffusion Equation discretized with the Finite Volume Method. Application to BWR. Annals of Nuclear Energy. 97:76-85. doi:10.1016/j.anucene.2016.06.023

Por favor, use este identificador para citar o enlazar este ítem: http://hdl.handle.net/10251/81249

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Title: Assembly Discontinuity Factors for the Neutron Diffusion Equation discretized with the Finite Volume Method. Application to BWR
Author:
UPV Unit: Universitat Politècnica de València. Escuela Técnica Superior de Ingenieros Industriales - Escola Tècnica Superior d'Enginyers Industrials
Universitat Politècnica de València. Escola Tècnica Superior d'Enginyeria Informàtica
Issued date:
Abstract:
The neutron flux spatial distribution in Boiling Water Reactors (BWRs) can be calculated by means of the Neutron Diffusion Equation (NDE), which is a space- and time-dependent differential equation. In steady state conditions, ...[+]
Subjects: Assembly Discontinuity Factor , Boiling Water Reactor , Neutron Diffusion Equation , Finite Volume Method , Eigenvalue problem
Copyrigths: Reserva de todos los derechos
Source:
Annals of Nuclear Energy. (issn: 0306-4549 )
DOI: 10.1016/j.anucene.2016.06.023
Publisher:
Elsevier Masson
Publisher version: http://dx.doi.org/10.1016/j.anucene.2016.06.023
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. 97 (2016) DOI 10.1016/j.anucene.2016.06.023.
Thanks:
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 projects ENE2014-59442-P, the Spanish Ministerio ...[+]
Type: Artículo

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