Experimental measurements are reported for nucleate boiling of various saturated liquid polyphenyls which are of interest as nuclear reactor coolants. Heat flux is presented as a function of the difference between the heater surface temperature and saturation temperature, and correlations by various semitheoretical methods are discussed. A peak heat flux is reported for all but one of the liquids tested, and good agreement is found with previous work with similar fluids. Methods are suggested which may be used to estimate the nucleate boiling characteristics of these liquids during forced convection at elevated pressures and liquid subcooling, even though the present tests include only pool boiling studies. These methods may be used in feasibility analyses of boiling-polyphenyl cooled and moderated reactors.