AbstractThis paper evaluates three-dimensional turbulent flow and convective heat transfer through mixing split vane in a single-phase and steady-state sub-channel of AP1000 nuclear reactor core by using general computational fluid dynamics code, Fluent6.3.26.Realizable K-ɛ model is used as a turbulent closure model, and the sub-channel is analyzed by numerical simulation. The results show that the mixing split vanes, which affect strongly the heat transfer in the sub-channel, are lateral flow, swirl and turbulent intensity between the sub-channels, and give reasonable agreements with experimental equations and AP1000 thermal hydraulic design
In this research, direct numerical simulations are performed for the evolution of a mixing layer in ...
The present paper deals with numerical analyses of coolant mixing in the reactor pressure vessel of...
Copyright © 2010 T. Höhne et al. This is an open access article distributed under the Creative Comm...
AbstractThis paper evaluates three-dimensional turbulent flow and convective heat transfer through m...
The development of new practices in nuclear research reactor safety aspects and optimization of rece...
International audienceThis work has been performed in the framework of the OECD-NEA thermalhydraulic...
Coolant mixing phenomena occurring in the pressure vessel of a nuclear reactor constitute one of the...
The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged ...
For the analysis of boron dilution transients and main steam linke break scenarios the modelling of ...
The numerical studies of turbulent heat transfer in separation flow presented in this paper. Enhance...
For the analysis of boron dilution transients and main steam line break scenarios the modelling of t...
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nucle...
Enhancing heat transfer between fuel rods and coolant is one of the main goals of nuclear engineerin...
Různé provozní podmínky pro tlakovodní reaktory (PWR) jsou charakterizovány několika jevy míšení, kt...
The objective of this PhD is to asses the capability of Computational Fluid Dynamics (CFD) to predic...
In this research, direct numerical simulations are performed for the evolution of a mixing layer in ...
The present paper deals with numerical analyses of coolant mixing in the reactor pressure vessel of...
Copyright © 2010 T. Höhne et al. This is an open access article distributed under the Creative Comm...
AbstractThis paper evaluates three-dimensional turbulent flow and convective heat transfer through m...
The development of new practices in nuclear research reactor safety aspects and optimization of rece...
International audienceThis work has been performed in the framework of the OECD-NEA thermalhydraulic...
Coolant mixing phenomena occurring in the pressure vessel of a nuclear reactor constitute one of the...
The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged ...
For the analysis of boron dilution transients and main steam linke break scenarios the modelling of ...
The numerical studies of turbulent heat transfer in separation flow presented in this paper. Enhance...
For the analysis of boron dilution transients and main steam line break scenarios the modelling of t...
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nucle...
Enhancing heat transfer between fuel rods and coolant is one of the main goals of nuclear engineerin...
Různé provozní podmínky pro tlakovodní reaktory (PWR) jsou charakterizovány několika jevy míšení, kt...
The objective of this PhD is to asses the capability of Computational Fluid Dynamics (CFD) to predic...
In this research, direct numerical simulations are performed for the evolution of a mixing layer in ...
The present paper deals with numerical analyses of coolant mixing in the reactor pressure vessel of...
Copyright © 2010 T. Höhne et al. This is an open access article distributed under the Creative Comm...