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10-15 May 2021
Virtual Event
Europe/Vienna timezone
The Conference will be held virtually from 10-15 May 2021

Collisional transport and poloidal asymmetry distribution of impurities in tokamak plasmas, with application to WEST

14 May 2021, 08:30
Virtual Event

Virtual Event

Regular Poster Magnetic Fusion Theory and Modelling P7 Posters 7


Patrick Maget (CEA)


The use of metallic walls as plasma facing components in tokamaks puts severe constraints on the control of impurity contamination. Heavy impurities like Tungsten are of particular concern due to the high level of radiative losses they can induce. Moreover, their high sensitivity to neoclassical transport mechanisms exacerbated by toroidal rotation or electrostatic potential asymmetry generally explains experimental cases of strong accumulation in the plasma core. The poloidal distribution of the impurity modulates the amplitude of this neoclassical transport [Angioni14], with an asymmetry that often leads to enhancement, but that can also result in a reduction of the flux [Helander98].
We report in this contribution on the development of an analytic model for a self-consistent determination of the poloidal asymmetry, collisional flux and steady state profile of heavy impurities [Maget20], with application to Tungsten transport in the WEST tokamak. The model is compared with nonlinear axisymmetric simulations with the XTOR code [Lütjens10,Ahn17,Maget20], and with computations using the drift-kinetic code NEO [Belli08]. Three main mechanisms drive the poloidal asymmetry of the impurity: centrifugal forces, electrostatic potential asymmetry and collisional friction with the main ion. In a geometrical formulation of this problem, the horizontal and vertical asymmetry parameters of the impurity density ($n_a$) move along a circle, with a centre and radius determined from the ion density and temperature gradients, and the angular position given by collisionality.

Horizontal ($\delta$) and vertical ($\Delta$) asymmetry parameters for a flat and a peaked ion temperature profile ($\eta_i=\partial_r\ln T_i/\partial_r\ln N_i$) when increasing the friction with the main ions.

In figure 1, the horizontal ($\delta=[n_a^{\theta=0}- n_a^{\theta=\pi}]/[n_a^{\theta=0}+ n_a^{\theta=\pi}]$) and vertical ($\Delta=[n_a^{\theta=\pi/2}- n_a^{\theta=-\pi/2}]/[n_a^{\theta=\pi/2}+ n_a^{\theta=-\pi/2}]$) asymmetry parameters, with $\theta$ the poloidal angle, are plotted at a given radial position for a flat and a peaked ion temperature profile when increasing the friction with the main ions ($\nu_a/\Omega_a$, with $\Omega_a=e_aB/m_a$).

Radial flow with and without poloidal asymmetry, as a function of the impurity charge (left), and in the $(\delta,\:\Delta)$ plane (right), for a peaked ion density.
The impurity flux is reduced by the growing negative horizontal asymmetry that originates from collisional friction with the main ion when the ion density profile is peaked (fig.2, right plots). A similar reduction also arises for a flat ion density case with the formation of a positive horizontal asymmetry. Simulations with XTOR, where the impurity behaviour is described via density and parallel momentum equations, confirm these results via an artificial collisionality scan, as shown in figure 3.

Horizontal ($\delta$) and vertical ($\Delta$) asymmetry parameters for a peaked ion density profile when varying the friction with the main ions (top), and ratio of the radial flow to the theoretical prediction without asymmetry in XTOR and in the model (bottom).

It can be shown that in the absence of toroidal rotation or anisotropic electrostatic potential, the steady state impurity distribution is however symmetric, so that the reduction of the flux affects the impurity profile in a transient way. Nonlinear simulations also reproduce the theoretical trajectory of the poloidal asymmetry during the evolution to steady state.
The analytical model also covers the effect of the electrostatic potential asymmetry, and allows computing the effect of a minority species with an anisotropic temperature, as driven during Ion Cyclotron Resonance Heating. If we isolate the effect of temperature anisotropy (disregarding ion temperature heating), we find, in agreement with NEO computations, that Tungsten is pushed toward the plasma core as the horizontal asymmetry is becoming negative, except in a narrow window where $T_\bot/T_\|$ is just above unity (fig. 4). This indicates that, in the absence of toroidal rotation, ion temperature heating has to compensate (via the increase of ion temperature screening effect) for a tendency to Tungsten accumulation.
Steady state Tungsten density peaking as a function of the minority $T_\bot/T_\|$  (top) and associated horizontal asymmetry (bottom) for a typical WEST plasma.

Aknowledgements: This work has been carried out within the framework of the French Research Federation for Fusion Studies, and of the EUROfusion Consortium. It has received funding from the Euratom research and training programme 2014–2018 and 2019–2020 under grant agreement No. 633053. We benefited from HPC resources from GENCI, from Marconi-Fusion and from Aix-Marseille Université project Equip@-Meso (ANR-10-EQPX-29-01).

[Angioni14] Angioni C. et al Plasma Physics and Controlled Fusion 56 (2014) 124001.
[Belli08] Belli E. et al Plasma Physics and Controlled Fusion 50 (2008) 095010.
[Helander98] Helander P. Physics of Plasmas 5 (1998) 3999.
[Lütjens10] Lütjens H. et al. Journal of Computational Physics 229 (2010) 8130.
[Ahn17] Ahn J-H et al Plasma Physics and Controlled Fusion 58 (2016) 125009.
[Maget20] Maget P. et al. Plasma Physics and Controlled Fusion 62 (2020) 025001.

Affiliation CEA
Country or International Organization France

Primary authors

Patrick Maget (CEA) Ms Judith Frank (Aix-Marseille Université) Dr Pierre Manas (CEA) Dr Timothée Nicolas (CNRS) Olivier Agullo (Aix-Marseille Université) Xavier Garbet (CEA) Hinrich Lütjens (Centre de Physique Théorique, Ecole Polytechnique, CNRS) Dr Jean-Francois Artaud Clarisse Bourdelle (CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France.) Laurent Colas (CEA, IRFM) Dr Remi Dumont (CEA, France )

Presentation Materials