Exploring fusion-reactor physics with high-power electron cyclotron resonance heating on ASDEX Upgrade

• Published in: Plasma physics and controlled fusion Vol. 62; no. 2; pp. 24012 - 24022
• Main Authors: Stober, J, Reisner, M, Angioni, C, Navarro, A Bañón, Bobkov, V, Bock, A, Denisov, G, Fable, E, Fischer, R, Gantenbein, G, Gil, L, Görler, T, Igochine, V, Kasparek, W, Leuterer, F, Litvak, A, McDermott, R, Meier, A, Monaco, F, Münich, M, Nichiporenko, V, Plaum, B, Plank, U, Poli, E, Popov, L, Pütterich, Th, Scherer, Th, Schubert, M, Suttrop, W, Tai, E, Thumm, M, Wagner, D, Zohm, H
• Format: Journal Article
• Language: English
• Published: IOP Publishing 01.02.2020
• Subjects: ECCD; ECRH; high-beta; non-inductive; q-profile; Tokamak
• ISSN: 0741-3335; 1361-6587; 1361-6587
• DOI: 10.1088/1361-6587/ab512b

The electron cyclotron resonance heating (ECRH) system of the ASDEX Upgrade tokomak has been upgraded over the last 15 years from a 2 MW, 2 s, 140 GHz system to an 8 MW, 10 s, dual frequency system (105/140 GHz). The power exceeds the L/H power threshold by at least a factor of two, even for high densities, and roughly equals the installed ion cyclotron range of frequencies power. The power of both wave heating systems together (>10 MW in the plasma) is about half of the available neutral beam injection (NBI) power, allowing significant variations of torque input, of the shape of the heating profile and of Qe/Qi, even at high heating power. For applications at a low magnetic field an X3-heating scheme is routinely in use. Such a scenario is now also forseen for ITER to study the first H-modes at one third of the full field. This versatile system allows one to address important issues fundamental to a fusion reactor: H-mode operation with dominant electron heating, accessing low collisionalities in full metal devices (also related to suppression of edge localized modes with resonant magnetic perturbations), influence of Te/Ti and rotational shear on transport, and dependence of impurity accumulation on heating profiles. Experiments on all these subjects have been carried out over the last few years and will be presented in this contribution. The adjustable localized current drive capability of ECRH allows dedicated variations of the shape of the q-profile and the study of their influence on non-inductive tokamak operation (so far at q95 > 5.3). The ultimate goal of these experiments is to use the experimental findings to refine theoretical models such that they allow a reliable design of operational schemes for reactor size devices. In this respect, recent studies comparing a quasi-linear approach (TGLF) with fully non-linear modeling (GENE) of non-inductive high-beta plasmas will be reported.