Critical Heat Flux Test at Idaho National Laboratory

Описание: Idaho National Laboratory conducted 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. Critical heat flux is the physical phenomenon that occurs when a fuel rod first begins to overheat and can no longer transfer additional heat to the water. This leads to excessive boiling around the surface of the pin and could potentially cause excessive fuel damage.

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