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Requirements on localized current drive for the suppression of neoclassical tearing modes

Author
Abstract

A heuristic criterion for the full suppression of an NTM was formulated as eta(NTM) = j(CD,max)/j(BS) >= 1.2 (Zohm et al 2005 J. Phys. Conf. Ser. 25 234), where j(CD,max) is the maximum in the driven current density profile applied to stabilize the mode and j(BS) is the local bootstrap current density. In this work we subject this criterion to a systematic theoretical analysis on the basis of the generalized Rutherford equation. Taking into account only the effect of j(CD) inside the island, a new criterion for full suppression by a minimum applied total current is obtained in the form of a maximum allowed value for the width of the driven current, w(dep), combined with a required minimum for the total driven current in the form of w(dep)eta(NTM), where both limits depend on the marginal and saturated island sizes. These requirements can be relaxed when additional effects are taken into account, such as a change in the stability parameter Delta' from the current driven outside the island, power modulation, the accompanying heating inside the island or when the current drive is applied preemptively. When applied to ITER scenario 2, the requirement for full suppression of either the 3/2 or 2/1 NTM becomes w(dep) less than or similar to 5 cm and w(dep)eta(NTM) greater than or similar to 5 cm in agreement with (Sauter et al 2010 Plasma Phys. Control. Fusion 52 025002). Optimization of the ITER ECRH Upper Port Launcher design towards minimum required power for full NTM suppression requires an increase in the toroidal injection angle of the lower steering mirror of several degrees compared with its present design value, while for the upper steering mirror the present design value is close to the optimum.

Year of Publication
2011
Journal
Nuclear Fusion
Volume
51
Issue
10
Number of Pages
15
Date Published
Oct
Type of Article
Article
ISBN Number
0029-5515
DOI
10.1088/0029-5515/51/10/103007
PId
45066441bb724ccc5f37f5334d645d12
Alternate Journal
Nucl. Fusion
Journal Article
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