Flow-induced vibration can lead to fretting wear damage of fuel rods and spacer grids in nuclear reactors. Similarly, during the transport of spent nuclear fuel assemblies, continuous vibration and intermittent impact might also result in fretting wear due to dynamic interaction. Therefore, it is important to evaluate fuel rod damage due to fretting wear under such transport conditions. This study examines spent nuclear fuel rod specimens fabricated with hydride cladding tubes and simulated pellets, with hydrogen content ranging from 200 to 700 ppm and oxide film thickness ranging from 25 to 100 micrometers. Tests were conducted under a worst-case scenario, assuming continuous exposure to that condition during the expected transport time. Results indicate that the wear depth of all rod specimens occurred within the oxide film, suggesting a high resistance to fretting wear during transportation.

• Jinseon Kim(KEPCO Nuclear Fuel (KEPCO NF)) Corresponding author
• Youngik Yoo(KEPCO Nuclear Fuel (KEPCO NF))
• Joongjin Kim(KEPCO Nuclear Fuel (KEPCO NF))
• Joonkyoo Park(KEPCO Nuclear Fuel (KEPCO NF))
• Hyeongkoo Kim(KEPCO Nuclear Fuel (KEPCO NF))