Abstract
In ITER, neutral beam (NB) heating and current drive (H&CD) system fires energetic particle beams of 1 MeV, 33 MW (16.5 MW/NB injector) into the fusion plasma. The design allows late installation of the third NB injector for upgrade in current drive experiment toward steady state operation. The ITER NB system has been designed to fulfill the requirements of the plasma physics, considering advanced scenario achieved with off-axis CD by NB. A design overview of the ITER NB H&CD system is described. The paper also reports the recent R&D status of ion source and accelerator, as key components of the NB system, toward ITER construction. The NB H&CD performance required in future tokamak reactors is discussed together with the necessary R&D issues.
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