Enhancing heat transfer between fuel rods and coolant is one of the main goals of nuclear engineering. Spacer grids equipped with mixing vanes are placed inside nuclear fuel assemblies to enhance the lateral velocities of the flow inside the sub-channels and, also, increase the lateral mixing between different sub-channels and, consequently, the heat transfer. For the design and analysis of these spacer grids, Computational Fluid Dynamics (CFD) tools, able to compute flow structures taking into account effects such as wall friction, turbulent mixing or heat transfer, are commonly used. In this project, CFD methodologies have been developed to simulate flow field inside bare rod bundle and bundles equipped with 4 types of spacers, tes...
Thermal-hydraulics is a key scientific subject to be investigated for the development of innovative ...
The design of rod bundles in nuclear application nowadays is assessed by CFD (computational fluid dy...
The design of rod bundles in nuclear application nowadays is assessed by CFD (computational fluid dy...
Enhancing heat transfer between fuel rods and coolant is one of the main goals of nuclear engineerin...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
Nuclear fuel bundles contain spacers essentially for mechanical stability and to influence the flow...
New and improved thermal hydraulic data is essential for ensuring safe operation for Pressurized Wat...
AbstractThe paper considers the flow and heat transfer in coolant flows cooling the fuel rod bundles...
This paper deals with a coarse-mesh Computational Fluid Dynamics (CFD) approach, referred to as Subc...
New and improved thermal hydraulic data is essential for ensuring safe operation for Pressurized Wat...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
Natural convection is a phenomenon in which a flow of the fluid surrounding a body is induced by a c...
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nucle...
Reactor fuel rod bundles serve as the primary heat source in light water reactors (LWRs), commonly f...
The design of rod bundles in nuclear application nowadays is assessed by CFD (computational fluid dy...
Thermal-hydraulics is a key scientific subject to be investigated for the development of innovative ...
The design of rod bundles in nuclear application nowadays is assessed by CFD (computational fluid dy...
The design of rod bundles in nuclear application nowadays is assessed by CFD (computational fluid dy...
Enhancing heat transfer between fuel rods and coolant is one of the main goals of nuclear engineerin...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
Nuclear fuel bundles contain spacers essentially for mechanical stability and to influence the flow...
New and improved thermal hydraulic data is essential for ensuring safe operation for Pressurized Wat...
AbstractThe paper considers the flow and heat transfer in coolant flows cooling the fuel rod bundles...
This paper deals with a coarse-mesh Computational Fluid Dynamics (CFD) approach, referred to as Subc...
New and improved thermal hydraulic data is essential for ensuring safe operation for Pressurized Wat...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
Natural convection is a phenomenon in which a flow of the fluid surrounding a body is induced by a c...
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nucle...
Reactor fuel rod bundles serve as the primary heat source in light water reactors (LWRs), commonly f...
The design of rod bundles in nuclear application nowadays is assessed by CFD (computational fluid dy...
Thermal-hydraulics is a key scientific subject to be investigated for the development of innovative ...
The design of rod bundles in nuclear application nowadays is assessed by CFD (computational fluid dy...
The design of rod bundles in nuclear application nowadays is assessed by CFD (computational fluid dy...