Performance of ITER as burning plasma experiment
M. Shimada1), V. Mukhovatov1), G. Federici2), Y. Gribov1), A. Kukushkin2), Y. Murakami3), A. Polevoi1), V. Pustovitov4), S. Sengoku5), M. Sugihara1)
1) International Team, ITER Naka JWS, Mukouyama, Naka-machi, Naka-gun, Ibaraki-ken, 311-0193, Japan,
2) International Team, ITER Garching JWS,
3) Toshiba Corp., Minato-ku, Tokyo
4) Kurchatov Institute, Moscow, Russia
5) Japan Atomic Energy Research Institute, Naka-machi, Ibaraki-ken, Japan
Abstract.
Recent performance analysis has improved confidence in achieving Q > 10 in inductive operation in ITER. Performance analysis based on empirical scaling shows the feasibility of achieving Q > 10 in inductive operation, particularly with improved modeling of helium exhaust. Analysis has also elucidated a possibility that ITER can potentially demonstrate Q's ~ 50, enabling studies of self-heated plasmas. Theory-based core modeling indicates the need of high pedestal temperature (2.3 - 4.5 keV) to achieve Q > 10, which is in the range of projection with presently available pedestal scalings. Pellet injection from high-field side would be useful in enhancing Q and reducing ELM heat load in high plasma current operation. If the ELM heat load is not acceptable, it could be made tolerable by further tilting the target plate. Steady state operation scenarios at Q = 5 have been developed with modest requirement on confinement improvement and beta (HH98(y,2) > 1.3 and 
> 2.6). Stabilisation of RWM, required in such regimes, is feasible with the present saddle coils and power supplies with double-wall structure taken into account. Recent analysis shows a potential of high power steady state operation with a fusion power of 0.7 GW at Q ~ 8. Achievement of the required ~ 3.6 by RWM stabilisation is a challenge and further analysis is also needed on the reduction of the divertor target heat load.