National Lab Unveils New Device to Probe Nuclear Fuel Safety Limits
2025-03-21
Idaho National Laboratory (INL) released footage of experiments conducted at its Transient Reactor Test Facility (TREAT). Using a novel device, they simulated the overheating of a nuclear fuel pin, focusing on critical heat flux—the point where a fuel rod can no longer transfer heat to the water. This research provides unique insights into fuel behavior under extreme conditions, helping determine safety limits and improve the efficiency of light-water reactors. The device will be used in future safety tests of advanced fuel designs, including accident-tolerant fuel tests in 2022, aiming to enhance heat transfer and maximize electricity production.