International audienceThe pressure and velocity distribution within and between full cross-section fuel assemblies with generic but realistic mixing grids are analyzed by CFD using high performance computing (HPC). The reference fuel assembly consists of a bundle of 17 × 17 rods, including fuel rods, control rod guide tubes and a mixing grid with split type mixing vanes. The axial length of the analyzed domain spans approximately the interval between two successive mixing grids. Only hydraulic effects of the mixing grids on the behavior of the flow are analyzed, power input and heat transfer are not considered.The presented results are based on a well-validated calculation procedure. The intra-assembly exchanges and pressure fields were ana...
International audienceWe present experimental results on 9 reduced-scale fuel assemblies arranged in...
AbstractThe fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles s...
This study presents a scaled-down single fuel assembly experiment to simulate the fuel in the spent ...
International audienceThe CALIFS study is part of a program that will combine hydraulic tests on 5 ×...
This paper presents the findings from a numerical simulation of the flow in 37-rod fuel assembly mod...
A study was made of hydraulic characteristics of Yankee-type fuel rod assemblies using experimental ...
Fuel assembly bow is an intricate industrial issue occurring in PWR nuclear cores, which relies on m...
International audienceCFD studies with the Trio_U code were performed to evaluate the flow field and...
International audienceIn nuclear Pressurized Water Reactors, fuel assemblies are slender structures ...
International audienceAbstract Fuel assemblies’ deformation is an industrial issue that has been fir...
As a new type of reactor fuel assembly, helical-cruciform fuel (HCF) assembly has some advantages. T...
The flow in fuel assemblies of PWRs with mixing grids has been analyzed with CFD calculations by num...
This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field ...
Graduation date: 2012The Hydro-Mechanical Fuel Test Facility (HMFTF) is being built at Oregon State ...
International audienceWe present experimental results on 9 reduced-scale fuel assemblies arranged in...
AbstractThe fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles s...
This study presents a scaled-down single fuel assembly experiment to simulate the fuel in the spent ...
International audienceThe CALIFS study is part of a program that will combine hydraulic tests on 5 ×...
This paper presents the findings from a numerical simulation of the flow in 37-rod fuel assembly mod...
A study was made of hydraulic characteristics of Yankee-type fuel rod assemblies using experimental ...
Fuel assembly bow is an intricate industrial issue occurring in PWR nuclear cores, which relies on m...
International audienceCFD studies with the Trio_U code were performed to evaluate the flow field and...
International audienceIn nuclear Pressurized Water Reactors, fuel assemblies are slender structures ...
International audienceAbstract Fuel assemblies’ deformation is an industrial issue that has been fir...
As a new type of reactor fuel assembly, helical-cruciform fuel (HCF) assembly has some advantages. T...
The flow in fuel assemblies of PWRs with mixing grids has been analyzed with CFD calculations by num...
This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field ...
Graduation date: 2012The Hydro-Mechanical Fuel Test Facility (HMFTF) is being built at Oregon State ...
International audienceWe present experimental results on 9 reduced-scale fuel assemblies arranged in...
AbstractThe fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles s...
This study presents a scaled-down single fuel assembly experiment to simulate the fuel in the spent ...