Critical Heat Flux (CHF) represents a concern for nuclear safety, as it leads to a rapid drop down in the heat transfer between a heated surface and the liquid coolant in the core of nuclear reactors. This could cause several issues to the system, including structural damage and release of radioactive material. The main challenges related to CHF predictions are the highly non-linear relationships with the physical features it depends on, and the two different underlying, microscopic phenomena that lead to CHF: Departure from Nucleate Boiling (DNB) and dryout, occurring under different conditions but not distinguishable externally, both resulting in the same outcome.