Requirements and design characteristics of the heating and current drive systems for KSTAR (Korean Super conducting Tokamak Advanced Research)1,2 tokamak are described. The neutral beam (NB), the ion cyclotron (IC), lower hybrid (LH) and electron cyclotron (EC) heating systems provide heating as well as current drive capability for long pulse lengths of up to 300 s. The systems are designed to provide flexibility in the control of current density and pressure profiles for the study of advanced tokamak plasmas.