Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor

The recirculation system of a BWR-5 has 20 jet pumps. They are submerged in water in the cylindrical annular zone of the reactor. Their main function is the development of a forcing flow through the nuclear core. It increases the power of the reactor compared with the one obtained by natural circula...

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Main Authors: G. Soto-Mendoza, A. Armenta-Molina, S. Pérez-Montejo, L.H. Hernández-Gómez, P. Ruiz-López, G.M. Urriolagoitia-Calderón, J.A. Beltrán-Fernández
Format: Article
Language:English
Published: Wiley 2021-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2021/8898343
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author G. Soto-Mendoza
A. Armenta-Molina
S. Pérez-Montejo
L.H. Hernández-Gómez
P. Ruiz-López
G.M. Urriolagoitia-Calderón
J.A. Beltrán-Fernández
author_facet G. Soto-Mendoza
A. Armenta-Molina
S. Pérez-Montejo
L.H. Hernández-Gómez
P. Ruiz-López
G.M. Urriolagoitia-Calderón
J.A. Beltrán-Fernández
author_sort G. Soto-Mendoza
collection DOAJ
description The recirculation system of a BWR-5 has 20 jet pumps. They are submerged in water in the cylindrical annular zone of the reactor. Their main function is the development of a forcing flow through the nuclear core. It increases the power of the reactor compared with the one obtained by natural circulation. These components have an important safety function in the operation of the reactor. In accordance with document BWRVIP-41 R4, it was concluded that the vibration induced by cross flow over the jet pump assemblies is one of the degradation mechanisms of such pumps. In this paper, the vibration induced by the cross flow at a jet pump assembly BWR-5 was analyzed. A numerical approach was developed. The natural frequencies were obtained, considering the Fluid-Structure Interaction (FSI). The first natural frequency was 25.7 Hz. A Computational Fluid Dynamics (CFD) analysis was carried, in conjunction with the Power Spectral Density (PSD). A frequency of vortex generation of 0.48 Hz was obtained. A vortex generation analysis was carried out with the Q-criteria. The results showed that resonance conditions are unlikely. Therefore, the structural integrity of the jet pump assemblies is maintained.
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spelling doaj-art-9f00bcc632184484a741874b35286fea2025-02-03T05:52:57ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832021-01-01202110.1155/2021/88983438898343Cross Flow Analysis over the Jet Pumps of a BWR-5 ReactorG. Soto-Mendoza0A. Armenta-Molina1S. Pérez-Montejo2L.H. Hernández-Gómez3P. Ruiz-López4G.M. Urriolagoitia-Calderón5J.A. Beltrán-Fernández6Instituto Politécnico Nacional, ESIME Unidad Zacatenco, Sección de Estudios de Posgrado e Investigación, Edificio 5, 3er. Piso, Unidad Profesional Adolfo López Mateos, Col. Lindavista, Alc. Gustavo A. Madero, 07738 Ciudad de México, MexicoInstituto Politécnico Nacional, ESIME Unidad Zacatenco, Sección de Estudios de Posgrado e Investigación, Edificio 5, 3er. Piso, Unidad Profesional Adolfo López Mateos, Col. Lindavista, Alc. Gustavo A. Madero, 07738 Ciudad de México, MexicoInstituto Politécnico Nacional, ESIME Unidad Zacatenco, Sección de Estudios de Posgrado e Investigación, Edificio 5, 3er. Piso, Unidad Profesional Adolfo López Mateos, Col. Lindavista, Alc. Gustavo A. Madero, 07738 Ciudad de México, MexicoInstituto Politécnico Nacional, ESIME Unidad Zacatenco, Sección de Estudios de Posgrado e Investigación, Edificio 5, 3er. Piso, Unidad Profesional Adolfo López Mateos, Col. Lindavista, Alc. Gustavo A. Madero, 07738 Ciudad de México, MexicoComisión Nacional de Seguridad Nuclear y Salvaguardias, Dr. José Ma. Barragán, No. 779, Colonia Narvarte, Alc. Benito Juárez, C.P. 03020, Ciudad de México, MexicoInstituto Politécnico Nacional, ESIME Unidad Zacatenco, Sección de Estudios de Posgrado e Investigación, Edificio 5, 3er. Piso, Unidad Profesional Adolfo López Mateos, Col. Lindavista, Alc. Gustavo A. Madero, 07738 Ciudad de México, MexicoInstituto Politécnico Nacional, ESIME Unidad Zacatenco, Sección de Estudios de Posgrado e Investigación, Edificio 5, 3er. Piso, Unidad Profesional Adolfo López Mateos, Col. Lindavista, Alc. Gustavo A. Madero, 07738 Ciudad de México, MexicoThe recirculation system of a BWR-5 has 20 jet pumps. They are submerged in water in the cylindrical annular zone of the reactor. Their main function is the development of a forcing flow through the nuclear core. It increases the power of the reactor compared with the one obtained by natural circulation. These components have an important safety function in the operation of the reactor. In accordance with document BWRVIP-41 R4, it was concluded that the vibration induced by cross flow over the jet pump assemblies is one of the degradation mechanisms of such pumps. In this paper, the vibration induced by the cross flow at a jet pump assembly BWR-5 was analyzed. A numerical approach was developed. The natural frequencies were obtained, considering the Fluid-Structure Interaction (FSI). The first natural frequency was 25.7 Hz. A Computational Fluid Dynamics (CFD) analysis was carried, in conjunction with the Power Spectral Density (PSD). A frequency of vortex generation of 0.48 Hz was obtained. A vortex generation analysis was carried out with the Q-criteria. The results showed that resonance conditions are unlikely. Therefore, the structural integrity of the jet pump assemblies is maintained.http://dx.doi.org/10.1155/2021/8898343
spellingShingle G. Soto-Mendoza
A. Armenta-Molina
S. Pérez-Montejo
L.H. Hernández-Gómez
P. Ruiz-López
G.M. Urriolagoitia-Calderón
J.A. Beltrán-Fernández
Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor
Science and Technology of Nuclear Installations
title Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor
title_full Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor
title_fullStr Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor
title_full_unstemmed Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor
title_short Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor
title_sort cross flow analysis over the jet pumps of a bwr 5 reactor
url http://dx.doi.org/10.1155/2021/8898343
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