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(EX8/3) Reactor Relevant Current Drive and Heating by N-NBI on JT-60U

T. Oikawa1), Y. Kamada1), A. Isayama1), T. Fujita1), T. Suzuki1), N. Umeda1), M. Kawai1), M. Kuriyama1), L. R. Grisham2), Y. I. Ikeda1), K. Kajiwara1), K. Ushigusa1), K. Tobita1), A. Morioka1), M. Takechi1), T. Itoh1) and the JT-60U Team
1) Japan Atomic Energy Research Institute, Naka, Japan
2) Princeton Plasma Physics Laboratory, USA.

Abstract.  Current drive capability of negative-ion-based NBI (N-NBI) in JT-60U has been extended to the reactor relevant regime. Driven current profile and current drive efficiency have been evaluated in the high temperature regime of central electron temperature Te(0) $ \sim$ 10keV, and reasonable agreement with theoretical prediction has been confirmed in this regime. N-NB driven current reached near 1MA with injection power of 3.75MW at beam energy of 360keV. The current drive efficiency of 1.55×1019Am- 2W- 1 approaching to the ITER requirement was achieved in the high $ \beta_{\mathrm{p}}^{}$ H mode plasma with Te(0) $ \sim$ 13keV. This current drive performance realized the sustainment of high beta ( $ \beta_{\mathrm{N}}^{}$ = 2.5) and high confinement ( HHy2 = 1.4) plasma in full current-driven condition at the plasma current of 1.5MA. The influence of instabilities on N-NB current drive was studied. When a burst like instability driven by N-NB occurred in the central region, reductions in loop voltage near magnetic axis and neutron production rate due to loss of beam ions were observed although the lost driven current was at most $ \sim$ 7% of the total driven current. When neoclassical tearing instability appeared in high beta plasmas, loss of beam ions was enhanced with increasing activity of instability and depended on the location of instability.

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IAEA 2001