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Analytical edge power loss at the lower hybrid resonance: ANTITER IV validation and application to ion cyclotron resonance heating systems

Published online by Cambridge University Press:  15 December 2021

V. Maquet*
Affiliation:
Laboratory for Plasma Physics - ERM/KMS, Avenue de la Renaissance 30, B-1000 Brussels Université Libre de Bruxelles, B-1050 Brussels
A. Druart
Affiliation:
Université Libre de Bruxelles, B-1050 Brussels International Solvay Institutes, CP 231, B-1050 Brussels
A. Messiaen
Affiliation:
Laboratory for Plasma Physics - ERM/KMS, Avenue de la Renaissance 30, B-1000 Brussels
*
Email address for correspondence: Vincent.Maquet@ulb.be
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Abstract

In the ion cyclotron range of frequency (ICRF), the presence of a lower hybrid (LH) resonance can appear in the edge of a tokamak plasma and lead to deleterious edge power depositions. An analytic formula for these losses is derived in the cold plasma approximation and for a slab geometry using an asymptotic approach and an analytical continuation near the LH resonance. The way to minimize these losses in a large machine like ITER is discussed. An internal verification between the power loss computed with the semi-analytical code ANTITER IV for ion cyclotron resonance heating (ICRH) and the analytic result is performed. This allows us to check the precision of the numerical integration of the singular set of cold plasma wave differential equations. The set of cold plasma equations used is general and can be applied in other parameters domain.

Information

Type
Research Article
Creative Commons
Creative Common License - CCCreative Common License - BY
This is an Open Access article, distributed under the terms of the Creative Commons Attribution licence (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted re-use, distribution and reproduction, provided the original article is properly cited.
Copyright
Copyright © The Author(s), 2021. Published by Cambridge University Press
Figure 0

Figure 1. ITER 2010 low electron density profile. The antenna and the LH resonance density are displayed.

Figure 1

Figure 2. The four plasma conductance matrix elements seen at the antenna position as a function of low $(k_y,k_z)$. The $k_z=\pm k_0$ line is also represented by red lines.

Figure 2

Figure 3. (a) Poynting flux jump observed around the LH resonance for a pair $(k_y,k_z)$ and for two dissipative terms. (b) Absolute value of the radial electric field $|E_x|$ around the LH resonance for a pair $(k_y,k_z)$ and for the same dissipative terms for a pure poloidal electric field excitation.

Figure 3

Figure 4. Power loss at the LH resonance for a pure $E_y(k_z,k_y)$ excitation. Red lines delimit the $|k_z|< k_0$. Here $k_0=1.15$ m$^{-1}$.

Figure 4

Figure 5. Power loss at the LH resonance for a pure $E_z(k_z,k_y)$ excitation. Red lines delimit the $|k_z|< k_0$. Here $k_0=1.15$ m$^{-1}$.

Figure 5

Figure 6. (a) Front face of the ITER antenna model used in ANTITER IV. (b) ITER 2012 ICRF antenna design showing the 24 strap array grouped in 8 triplets with their feeding a quarter of the array is shown with the Faraday screen removed (Lamalle et al.2013).

Figure 6

Figure 7. An antenna box and a FS aligned to the magnetic field. (a) The $k_z$ power spectrum and (b) $k_z$ edge power loss spectrum for a current distribution on straps of 1 A and three different toroidal phasings. A poloidal phasing of ${\rm \pi} /2$ is imposed for load resilience. The toroidal phasing $(0.0,2.9,3.7,0.3)$ rad minimizes the edge LH power losses.

Figure 7

Figure 8. A misaligned antenna box and an aligned FS. (a) The $k_z$ power spectrum and (b) $k_z$ edge power loss spectrum for a current distribution on straps of 1 A and three different toroidal phasings. A poloidal phasing of ${\rm \pi} /2$ is imposed for load resilience. The toroidal phasing $(0.0,2.9,3.7,0.3)$ rad minimizes the edge LH power losses.

Figure 8

Figure 9. A misaligned antenna box and a misaligned FS. (a) The $k_z$ power spectrum and (b) $k_z$ edge power loss spectrum for a current distribution on straps of 1 A and three different toroidal phasings. A poloidal phasing of ${\rm \pi} /2$ is imposed for load resilience. The toroidal phasing $(0.0,2.9,3.7,0.3)$ rad minimizes the edge LH power losses.

Figure 9

Figure 10. Map showing respectively: (a) the percentage of power loss in the edge and (b) the integrated radial electric field $\iint |E_x|^2\, \mathrm {d}k_y\, \mathrm {d}k_z$ at the LH resonance as a function of the power ratio $P_{central}/P_{tot}$ and a central phase deviation ${\rm \Delta} \phi$ from the phasing minimizing the edge power loss $(0,2.9+{\rm \Delta} \phi,3.7+{\rm \Delta} \phi,0.3)$.

Figure 10

Figure 11. (a) Density profile constructed with exponential decaying lengths considered. (b) Corresponding increase of edge power losses as a function of the decay length considered and an even current strap excitation.

Figure 11

Figure 12. (a) Density profile constructed with the same exponential decaying lengths crossing the LH resonance at different position. (b) Corresponding increase of edge power losses as a function of the LH position considered and an even current strap excitation.