Méndez Díaz, Santos(Universitat Politècnica de València, 2008-09-30)
En años recientes se han realizado esfuerzos para incrementar la compresión de los fenómenos asociados al flujo bifásico líquido - gas, para lo cual se han establecido modelos matemáticos que intentan reflejar el comprotamiento ...
[ES] El uso de los códigos de Dinámica de Fluidos Computacional (CFD) 3D para predecir el flujo
estacionario y transitorio en los reactores nucleares está creciendo rápidamente y constituye una
nueva tendencia en su ...
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 ...
[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 ...
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 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 ...
The OECD/NEA ROSA project test 1-1 was conducted in 2006 with
the objective to obtain the multidimensional temperature distributions in cold legs
and downcomer during the Emergency Core Cooling System (ECCS) water ...