[ES] En las últimas décadas se ha destinado un esfuerzo considerable al desarrollo
del campo de códigos termo-hidráulicos, pudiendo con estos simular el comportamiento de un
reactor ante transitorios y accidentes. Acuerdos ...
Harby, K.; Chiva, S.; Muñoz-Cobo, J. L.(Elsevier, 2017)
[EN] In this article, an experimental and theoretical study on the buoyant non-condensable gas jet that is injected horizontally into a high-density liquid ambient at different initial conditions is performed. Direct and ...
Domínguez, Dany S.; Iglesias, Susana M.; Muñoz-Cobo, J. L.; Escrivá, Alberto; Berna, César; Rivera-Durán, Yago(Sociedad Nuclear Española, 2019-09-28)
[ES] Películas de agua gobernadas por gravedad en tuberías verticales son relevantes en
diversos procesos industriales asociados a intercambiadores de calor, evaporadores y reactores
nucleares. La formación de ondas y el ...
[EN] Turbulent jet discharges in subcooled water pools are essential for safety systems in nuclear power plants, specifically in the pressure suppression pool of boiling water reactors and In-containment Refueling Water ...
Escrivá Castells, Facundo Alberto; Muñoz-Cobo González, José Luís; Concejal, A.; Soler, A.; Melara San Román, José; Albendea, M.(Sociedad Nuclear Española, 2013-09)
Las herramientas de simulación SNAP-TRACE están siendo
desarrolladas y actualizadas por la NRC y el grupo de usuarios de las mismas, con el
fin de que simulen el comportamiento termohidráulico de una instalación o ...
[EN] The one-dimensional two-fluid model approach has been traditionally used in thermal-hydraulics codes for the analysis of
transients and accidents in water¿cooled nuclear power plants. This paper investigates the ...
Nuclear fuel bundles contain spacers essentially for mechanical stability and to influence the
flow dynamic and heat transfer phenomena along the fuel rods. This work presents the analysis
of the turbulence effects of a ...
Melara San Román, José(Universitat Politècnica de València, 2016-03-01)
[EN] Power and flow oscillations in a BWR are very undesirable. One of the major concerns is to ensure, during power oscillations, compliance with GDC 10 and 12. GDC 10 requires that the reactor core be designed with ...
Blanco, D.; Berna, C.; Escrivá, A.; Muñoz-Cobo, J. L.; Sánchez, M.; Pérez, J.(Sociedad Nuclear Española, 2019-09-28)
[ES] El desarrollo de códigos termo-hidráulicos lleva muchos años avanzando debido a los
esfuerzos invertidos en ellos. Mediante ellos, se reproduce el comportamiento ante accidentes y
transitorios en reactores consiguiendo ...
[EN] Annular flow is characterized by a thin liquid film flowing on the pipe wall and a high velocity gas core flowing in its center, which normally carries liquid droplets. This review presents and analyzes most of the ...
[EN] Annular two-phase flow has been vastly investigated because of its large and deep involvement in industrial processes, particularly in nuclear engineering. This paper reviews most of the recent literature on the matter, ...
Muñoz-Cobo, J. L.; Blanco, D.; Berna, C.; Córdova, Y.(Elsevier, 2022-11)
[EN] The purpose of this paper is to review and analyze several types of instabilities as condensation oscillations (CO), stable condensation oscillations (SC), and bubbling condensation oscillation (BCO). These instabilities ...
Romero Hamers, Adolfo; Muñoz-Cobo González, José Luís; Chiva Vicent, Sergio; Posada, José María; Martínez-Murillo, J.C.(Sociedad Nuclear Española, 2013-09)
La presente ponencia presenta un análisis realizado con el código
TRACE del transitorio RESA que tuvo lugar en la Central Nuclear de Trillo en el año
2001. La comparación de los resultados de TRACE con los de planta ...
[EN] A set of two phase flow experiments for different conditions ranging from bubbly flow to cap/slug flow have been performed under isothermal concurrent upward air-water flow conditions in a vertical column of 3m height. ...
Romero Hamers, Adolfo(Editorial Universitat Politècnica de València, 2014-03-20)
In the event of hypothetical accident scenarios in PWR, emergency strategies have to be mapped out, in order to guarantee the reliable removal of decay heat from the reactor core, also in case of component breakdown. One ...
Muñoz-Cobo, J. L.; Berna, C.; Escrivá, A.(Elsevier, 2018)
[EN] The scaling methodology describes quantitatively the possible differences in the behavior between a reduced size experimental facility and a full scale commercial plant for a determined transient. Then scaling is an ...
Muñoz-Cobo González, José Luís; Chiva Vicent, Sergio; ESSA, M. A. Abdelaziz; Mendes, Santos(Multi-Science Publishing, 2012-09-01)
A set of air-water experiments has been performed under isothermal upward concurrent flow conditions, in a vertical column. The interfacial velocity, the bubble interfacial area and the void fraction distributions have ...
Las herramientas de simulación SNAP-TRACE están siendo desarrolladas y actualizadas por
la NRC y el grupo de usuarios de las mismas, con el fin de que simulen el comportamiento
termohidráulico de una instalación o central ...