The nuclear industry has a long history of usage of reliable and well-validated software for design and safety analysis of nuclear power generation systems. However, the majority of codes employed are based on the assumption that the flow is essentially one-dimensional, and they often provide excessively conservative predictions when three-dimensional phenomena have a significant influence. The aims of this study are twofold: - Furthering the understanding of three-dimensional flow patterns that may occur within the AGR fuel stringer during refuelling operations. - Developing a numerical tool for refuelling cooling analysis capable of supporting the existing methodology in scenarios where neglecting three-dimensional phenomena would...
Natural convection is a phenomenon in which a flow of the fluid surrounding a body is induced by a c...
The present work deals with the application of single-phase and two-phase Computational Fluid Dynami...
A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel ...
This thesis studies the cooling of rod bundles within the Advanced Gas-cooled Reactor (AGR) fuel rou...
The thermal hydraulic analysis of nuclear reactors is largely performed by what are known as system...
The research and development of advanced nuclear reactors requires complementary experimental and co...
The research and development of advanced nuclear reactors requires complementary experimental and co...
A computational fluid dynamics code is used to model the primary natural circulation loop of a propo...
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nucle...
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. Howev...
Nationwide, the demand for electricity due to population and industrial growth is on the rise. Howev...
Two mathematical models (a one and a three-dimensional) were adopted to study, numerically, the ther...
Analytical methods and Computational Fluid Dynamics (CFD) examined the safety and performance of adv...
Analytical methods and Computational Fluid Dynamics (CFD) examined the safety and performance of adv...
This work is part of a benchmarking excise organized by IAEA CRP in SCWR thermal-hydraulics aimed at...
Natural convection is a phenomenon in which a flow of the fluid surrounding a body is induced by a c...
The present work deals with the application of single-phase and two-phase Computational Fluid Dynami...
A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel ...
This thesis studies the cooling of rod bundles within the Advanced Gas-cooled Reactor (AGR) fuel rou...
The thermal hydraulic analysis of nuclear reactors is largely performed by what are known as system...
The research and development of advanced nuclear reactors requires complementary experimental and co...
The research and development of advanced nuclear reactors requires complementary experimental and co...
A computational fluid dynamics code is used to model the primary natural circulation loop of a propo...
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nucle...
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. Howev...
Nationwide, the demand for electricity due to population and industrial growth is on the rise. Howev...
Two mathematical models (a one and a three-dimensional) were adopted to study, numerically, the ther...
Analytical methods and Computational Fluid Dynamics (CFD) examined the safety and performance of adv...
Analytical methods and Computational Fluid Dynamics (CFD) examined the safety and performance of adv...
This work is part of a benchmarking excise organized by IAEA CRP in SCWR thermal-hydraulics aimed at...
Natural convection is a phenomenon in which a flow of the fluid surrounding a body is induced by a c...
The present work deals with the application of single-phase and two-phase Computational Fluid Dynami...
A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel ...