Recent DIII-D results demonstrate that the snowflake (SF) divertor geometry (cf. standard divertor) enables significant manipulation of divertor heat transport for heat spreading and reduction in attached and radiative divertor regimes, between and during edge localized modes (ELMs), while maintaining good H-mode confinement. Increased integral scrapeoff layer (SOL) width and heat flux spreading over additional strike points (SPs) were observed in DIII-D, suggesting enhanced heat transport through the low poloidal field nullpoint region and divertor legs. Direct measurements of divertor null-region poloidal βp, using a unique DIII-D divertor Thomson scattering diagnostic, were consistent with the theoretically proposed mechanism of instability-driven fast convective plasma mixing in the high-βp region, especially efficient during ELMs. The peeling-ballooning mode stability in the H-mode discharges was not significantly affected in the SF configuration as the ELM frequency and size were changed by 10-20 %. The stored energy lost per ELM (i.e., ELM size) was reduced. In deuterium-seeded radiative regimes in 4-5 MW NBI-heated H-mode discharges, the SF geometry led to a significant reduction of peak heat fluxes between and during ELMs. The results complement the initial SF divertor studies in the NSTX and DIII-D tokamaks and contribute to the physics basis of the radiative SF divertor as a power exhaust concept for future tokamaks.