Tag Archives: Accident-tolerant fuel
Post-Irradiation Examination of Molybdenum Rings and Discs Constraining Ultrahigh-Burnup Uranium Dioxide Fuel Discs
Molybdenum-based alloys are under investigation as a potential material for light water reactor fuel cladding to enhance the accident tolerance of nuclear fuel rods, but more data is needed on key alloy properties. This study examined five irradiated molybdenum samples and one unirradiated sample with a light optical microscope, scanning electron microscope, and other technologies.
While the reliability of zirconium alloys for nuclear fuel cladding in light water reactors has been excellent, the Fukushima accident illustrated the vulnerability of these alloys to rapid steam oxidation during a severe accident when the reactor core is interrupted for a long time. EPRI has conducted a feasibility study for a coated molybdenum alloy […]