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National Lab Creates New Device to Test Safety Limits of Nuclear Fuel
INL conducted experiments at its TREAT Facility using a first-of-a-kind device that can detect and study what happens to a nuclear fuel pin when it starts to overheat.
INL conducted the experiments at its Transient Reactor Test Facility (TREAT) using a first-of-a-kind device that can detect and study the critical heat flux of a nuclear fuel rod. The slow-motion video by INL shows the progression of boiling leading up to the point where critical heat flux is reached, when large quantities of water vapor bubbles touch the surface of the fuel rod. “Critical heat flux is an important parameter that regulators use to determine the safety limits of nuclear fuel,” said Dr. Colby Jensen, the Transient Testing Technical Leader.
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