Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2014.Cataloged from PDF version of thesis.Includes bibliographical references (pages 83-84).Grid-to-rod fretting (GTRF) has been the major cause of fuel leakage in Pressurized Water Reactors (PWRs) for the past ten years. It is responsible for over 70% of the fuel leaking in PWRs in the United States. The Consortium for Advanced Simulation of Light Water Reactors (CASL) has identified GTRF as one of the "Challenge Problems" that motivates the need for development and application of a modeling environment for predictive simulation of light water reactors. In this thesis, an initial verification of the Fluid Structure interaction (FSI) coupling...
The release of fissile material into the coolant caused by fretting of the fuel rods at the interfac...
Fretting damage to fuel rods reduces the service lives of the fuel assemblies and therefore increase...
This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field ...
International audienceFlow-induced vibrations in a pressurized water reactor (PWR) core can cause fr...
AbstractThe fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles s...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
The following report presents an assessment of existing capabilities in Sierra/Fuego applied to mode...
International audienceForces exerted by the water coolant flow in nuclear reactor cores result in fu...
PWRs fuel assemblies utilize spacer grids with flow mixing vanes to augment the coolant turbulence a...
The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged ...
Fluid flows through rod bundles are observed in many nuclear applications, such as in the core of Ge...
International audienceA coolant flow is used in Pressurized-Water Reactors (PWR) cores to extract th...
International audienceIdentifying what causes fuel assembly vibrations downstream of Mixing Vane Gri...
Reactor fuel rod bundles serve as the primary heat source in light water reactors (LWRs), commonly f...
Graduation date: 2015As computational power increases, so does the desire to use fluid-structure int...
The release of fissile material into the coolant caused by fretting of the fuel rods at the interfac...
Fretting damage to fuel rods reduces the service lives of the fuel assemblies and therefore increase...
This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field ...
International audienceFlow-induced vibrations in a pressurized water reactor (PWR) core can cause fr...
AbstractThe fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles s...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
The following report presents an assessment of existing capabilities in Sierra/Fuego applied to mode...
International audienceForces exerted by the water coolant flow in nuclear reactor cores result in fu...
PWRs fuel assemblies utilize spacer grids with flow mixing vanes to augment the coolant turbulence a...
The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged ...
Fluid flows through rod bundles are observed in many nuclear applications, such as in the core of Ge...
International audienceA coolant flow is used in Pressurized-Water Reactors (PWR) cores to extract th...
International audienceIdentifying what causes fuel assembly vibrations downstream of Mixing Vane Gri...
Reactor fuel rod bundles serve as the primary heat source in light water reactors (LWRs), commonly f...
Graduation date: 2015As computational power increases, so does the desire to use fluid-structure int...
The release of fissile material into the coolant caused by fretting of the fuel rods at the interfac...
Fretting damage to fuel rods reduces the service lives of the fuel assemblies and therefore increase...
This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field ...