Quenching Experiments with CrAl-coated Zircaloy Cladding in Reflooding Water Flows

A quenching experiment is performed to investigate the heat transfer characteristics and cooling performance of CrAl-coated Zircaloy (Zr) cladding in a water flow. The Zr one accident tolerant fuels for light reactors. uncoated also used this comparison. This simulates reflood fuel rod during loss coolant (LOCA) nuclear power plant. test conditions were determined represent peak temperature, subcooling velocity event LOCA. flow visualization showed film boiling early stage transition nucleate boiling. layer decreases as increases becomes wavy increases. more thinner than cladding. rewetting temperature initial wall and/or quench front significantly has negligible effect on velocity.