ITER operational space for full plasma current H-mode operation

Sensitivity studies performed as part of the ITER IO design review highlighted a very stiff dependence of the maximum Q attainable on the machine parameters. In particular, in the considered range, the achievable Q scales with I p ^4. As a consequence, the achievement of the ITER objective of Q = 10...

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Bibliographic Details
Published in:	Fusion engineering and design 2009-06, Vol.84 (2), p.300-304
Main Authors:	Mattei, M., Cavinato, M., Saibene, G., Portone, A., Albanese, R., Ambrosino, G., Horton, L.D., Kessel, C., Koechl, F., Lomas, P.J., Nunes, I., Parail, V., Sartori, R., Sips, A.C.C., Thomas, P.R.
Format:	Article
Language:	eng
Subjects:	Applied sciences Coiling Conductors (devices) Controled nuclear fusion plants Design engineering Energy Energy. Thermal use of fuels Exact sciences and technology Exploration Installations for energy generation and conversion: thermal and electrical energy Magnet system Plasma control Plasma currents Plasma engineering Proposals Scenario Shape control Solenoids
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Summary:	Sensitivity studies performed as part of the ITER IO design review highlighted a very stiff dependence of the maximum Q attainable on the machine parameters. In particular, in the considered range, the achievable Q scales with I p ^4. As a consequence, the achievement of the ITER objective of Q = 10 requires the machine to be routinely operated at a nominal current I p of 15 MA, and at full toroidal field BT of 5.3 T. This paper analyses the capabilities of the poloidal field (PF) system (including the central solenoid) of ITER against realistic full current plasma scenarios. An exploration of the ITER operational space for the 15 and 17 MA inductive scenario is carried out. An extensive analysis includes the evaluation of margins for the closed loop shape control action. The overall results of this analysis indicate that the control of a 15 MA plasma in ITER is likely to be adequate in the range of li 0.7–0.9 whereas, for a 17 MA plasma, control capabilities are strongly reduced. The ITER operational space, provided by the reference pre-2008 PF system, was rather limited if compared to the range of parameters normally observed in present experiment. Proposals for increasing the current and field limits on PF2, PF5 and PF6, adjustment on the number of turns in some of the PF coils, changes to the divertor dome geometry, to the conductor of PF6 to Nb3Sn, moving PF6 radially and/or vertically are described and evaluated in the paper. Some of them have been included in 2008 ITER revised configuration.
ISSN:	0920-3796 1873-7196