Measurements of heat-flux profiles on the divertor targets of Alcator C-Mod

Acceptable power handling is one of the primary functions - and most challenging problems - for a tokamak divertor. A section of C-Mod's outer divertor has been modified and instrumented in order to measure the incident heat-flux there. Surface temperatures are measured using IR thermography, and the heat-flux ``footprints'' are derived from those measurements. Peak surface-normal heat fluxes greater than 15 MW/m$^{2}$, corresponding to parallel heat-fluxes $>$ 300 MW/m$^{2}$, are typical in both EDA H-modes and RF-heated L-modes. In EDA H-modes widths (FWHM) of the main peak of the heat-flux profiles are in the range 1.5-4 mm (magnetically mapped to the midplane), and these values help to constrain the major radius and magnetic field dependencies of multi-machine empirical scaling relations for SOL heat-flux widths. Also evident in the heat-flux profiles is a far-SOL ``tail'' with constant or slowly decreasing heat-flux. Scalings of the ``footprint'' profile widths with various ``engineering'' parameters, as well as with the SOL pressure profile widths of the main plasma, will be presented.