Standard operation of a next-step tokamak aims to exploit the divertor ELMy H-mode regime. However, its best performance is hampered by low frequency, but large, Type I ELM fluctuations which would imply severe intermittent loads on boundary surfaces. Moderation of ELMs without degrading confinement therefore remains a high priority for fusion plasmas. On the Alcator C-Mod device using Ohmic or RF auxiliary heating with strong shaping, a quasi-stationary state has been demonstrated which has high density and good energy confinement, but no or only modest ELMs, exhibiting instead substantially increased edge recycling.