Grid-to-rod flow-induced impact study for PWR fuel in reactor
Dynamic contact impact from hydraulic flow-induced fuel assembly vibration is the source for
grid-to-rod fretting in a pressurized water nuclear reactor (PWR). To support grid-to-rod …
grid-to-rod fretting in a pressurized water nuclear reactor (PWR). To support grid-to-rod …
Review of spacer grid to rod fretting in pressurized water reactor
G Ricciardi, V Faucher, L Rossi, F François… - … Engineering and Design, 2024 - Elsevier
In spite of the low fuel failure rate in currently operating water cooled nuclear power reactors,
operations are increasingly demanding with higher burn-up, power increases, cycle lengths …
operations are increasingly demanding with higher burn-up, power increases, cycle lengths …
Numerical modeling of flow induced vibration of nuclear fuel rods
D De Santis, A Shams - Nuclear Engineering and Design, 2017 - Elsevier
Flow induced vibration (FIV) plays an important role in many industrial applications,
including nuclear energy. In a nuclear power plant, several components could experience …
including nuclear energy. In a nuclear power plant, several components could experience …
Numerical simulation study on the fluid excitation force on a nuclear fuel rod with a spacer grid
Y Wang, M Zheng, J Zhang, Y Jiao, Y Wu, W Tian… - Annals of Nuclear …, 2023 - Elsevier
Fluid excitation force is the driving source of grid-to-rod fretting (GTRF) wear, which is an
important mechanism of nuclear fuel failure and breakage. In the present work, the fluid …
important mechanism of nuclear fuel failure and breakage. In the present work, the fluid …
Large-eddy simulation, fuel rod vibration and grid-to-rod fretting in pressurized water reactors
Grid-to-rod fretting (GTRF) in pressurized water reactors is a flow-induced vibration
phenomenon that results in wear and fretting of the cladding material on fuel rods. GTRF is …
phenomenon that results in wear and fretting of the cladding material on fuel rods. GTRF is …
Issues and future direction of thermal-hydraulics research and development in nuclear power reactors
P Saha, N Aksan, J Andersen, J Yan… - … Engineering and Design, 2013 - Elsevier
The paper archives the proceedings of an expert panel discussion on the issues and future
direction of thermal-hydraulic research and development in nuclear power reactors held at …
direction of thermal-hydraulic research and development in nuclear power reactors held at …
Spectral element applications in complex nuclear reactor geometries: Tet-to-hex meshing
The spectral element code Nek5000 is an open-source, higher-order computational fluid
dynamics code developed at Argonne National Laboratory. It is designed to solve …
dynamics code developed at Argonne National Laboratory. It is designed to solve …
Experiments on the localized interaction at the interface fuel rod/spacer grid in pressurized water reactors
The release of fissile material into the coolant caused by fretting of the fuel rods at the
interface with spacer grids is a significant safety issue and cause of financial losses in the …
interface with spacer grids is a significant safety issue and cause of financial losses in the …
A validated numerical methodology for flow-induced vibration of a semi-spherical end cantilever rod in axial flow
This study presents a simulation method for turbulent flow-induced vibrations of cantilever
rods with a semi-spherical end exposed to axial flow, a configuration investigated for the first …
rods with a semi-spherical end exposed to axial flow, a configuration investigated for the first …
Axial-flow-induced vibration experiments on cantilevered rods for nuclear reactor applications
Axial-flow-induced vibration has been experimentally investigated with clamped-free
cantilevered cylindrical rods confined in a tube and subjected to axial water flow directed …
cantilevered cylindrical rods confined in a tube and subjected to axial water flow directed …