Abstract
We identify critical problems in Plasma Heating and Current Drive plasma-wave interaction physics and antennae concepts/technology for large fusion devices, including tokamaks, stellarators, mirror traps and constructing ITER for major methods like ECRF, ICRF, NBI. Analysis is based on experiments in large machines and modeling with 3D ICRF and ECRF recently developed full wave PSTELION and STELEC codes, including mode conversion, 3D in-port antennae ANPORT and ANTRES3 codes and theoretical evaluations. We outline identified problems resolution by: 1) elaborated 3D RF full wave codes modeling, 2) proposing High Frequency Fast Waves (HFFW) numerically modeled scheme for DIII-D and ITER, 3) considering principally new approach for ICRH/CD method, especially in conditions of transient ELM activity, making use toroidally broad multi loop Traveling Wave Antenna (TWA) concept which naturally incorporates antenna's loops inter coupling through vacuum and plasma with elegant control of antenna-plasma coupling through a small generator frequency change to properly control toroidal wave's spectrum during plasma edge density profile reconstruction.
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