Fuel rod clad Coolant bubbles Vapor film (post-DNB)
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Critical Heat Flux & DNBR Boiling Curve Simulator (2D)

Every pressurized-water reactor is operated against one governing thermal-hydraulic limit: the departure from nucleate boiling ratio (DNBR), the margin between the heat flux a fuel rod is actually delivering and the critical heat flux at which the coolant film on its surface collapses into an insulating vapor blanket. This 2D simulator renders a scrollable coolant-channel cross-section with an animated bubble field alongside a live boiling-curve plot, computing a real Zuber-correlation critical heat flux from system pressure and applying flow and subcooling corrections exactly as core thermal design does, so you can push heat flux, pressure, coolant mass flux and subcooling until the rod crosses from stable nucleate boiling into a modeled boiling crisis and watch both the rod view and the curve respond in real time.