Assessing wall heat fluxes in the quasi-continuous exhaust regime at ASDEX Upgrade

Abstract The 3D fluid edge code EMC3-EIRENE has been used to simulate three ASDEX Upgrade discharges with the same equilibrium but different upstream collisionality <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msup> <mml:mi>ν</mml:mi> <mml:mo>∗</mml:mo> </mml:msup> </mml:mrow> </mml:math> . In this scan, the plasma transits from an ELMy state at low collisionality to being in the quasi-continuous exhaust regime (QCE) at high <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msup> <mml:mi>ν</mml:mi> <mml:mo>∗</mml:mo> </mml:msup> </mml:mrow> </mml:math> . Particular attention was devoted to matching the experimental plasma profiles in front of the ion cyclotron resonance heating (ICRH) limiter, aiming to obtain a reliable estimation of the ICRH limiter peak heat flux in the QCE regime discharge. As a result, we observed that while moving from ELMy to QCE, the limiter peak heat flux increases, reaching values in the order of the <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mrow> <mml:mi>MW</mml:mi> <mml:mstyle scriptlevel="0"/> <mml:msup> <mml:mi mathvariant="normal">m</mml:mi> <mml:mrow> <mml:mo>−</mml:mo> <mml:mn>2</mml:mn> </mml:mrow> </mml:msup> </mml:mrow> </mml:mrow> </mml:math> for a limiter-separatrix distance of <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mrow> <mml:mn>6</mml:mn> <mml:mstyle scriptlevel="0"/> <mml:mi>cm</mml:mi> </mml:mrow> </mml:mrow> </mml:math> . These values were compared with those at the outer divertor, measured by infrared thermography, revealing that the heat flux perpendicular to the limiter surface can reach up to 90% of the one impinging onto the outer target. Finally, an attempt was made to extend the obtained results towards ITER. This simple analysis suggests that a large wall clearance and a small incidence angle of the magnetic field line, not only on the divertor target but also on ITER’s first wall, might have a crucial role in preventing wall damage during QCE discharges.

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Journal
Nuclear Fusion
Published
2026-03-02
DOI
https://doi.org/10.1088/1741-4326/ae4bf5
Primary Topic
Magnetic confinement fusion research
Type
article
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article

Assessing wall heat fluxes in the quasi-continuous exhaust regime at ASDEX Upgrade

M. Faitsch, G. Grenfell, A. Redl, Luca Scotti et al.
Nuclear Fusion
Magnetic confinement fusion research
article

Assessing wall heat fluxes in the quasi-continuous exhaust regime at ASDEX Upgrade

M. Faitsch, G. Grenfell, A. Redl, Luca Scotti, the ASDEX Upgrade Team, the EUROfusion Tokamak Exploitation Team
article en

Abstract

Abstract The 3D fluid edge code EMC3-EIRENE has been used to simulate three ASDEX Upgrade discharges with the same equilibrium but different upstream collisionality <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msup> <mml:mi>ν</mml:mi> <mml:mo>∗</mml:mo> </mml:msup> </mml:mrow> </mml:math> . In this scan, the plasma transits from an ELMy state at low collisionality to being in the quasi-continuous exhaust regime (QCE) at high <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msup> <mml:mi>ν</mml:mi> <mml:mo>∗</mml:mo> </mml:msup> </mml:mrow> </mml:math> . Particular attention was devoted to matching the experimental plasma profiles in front of the ion cyclotron resonance heating (ICRH) limiter, aiming to obtain a reliable estimation of the ICRH limiter peak heat flux in the QCE regime discharge. As a result, we observed that while moving from ELMy to QCE, the limiter peak heat flux increases, reaching values in the order of the <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mrow> <mml:mi>MW</mml:mi> <mml:mstyle scriptlevel="0"/> <mml:msup> <mml:mi mathvariant="normal">m</mml:mi> <mml:mrow> <mml:mo>−</mml:mo> <mml:mn>2</mml:mn> </mml:mrow> </mml:msup> </mml:mrow> </mml:mrow> </mml:math> for a limiter-separatrix distance of <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mrow> <mml:mn>6</mml:mn> <mml:mstyle scriptlevel="0"/> <mml:mi>cm</mml:mi> </mml:mrow> </mml:mrow> </mml:math> . These values were compared with those at the outer divertor, measured by infrared thermography, revealing that the heat flux perpendicular to the limiter surface can reach up to 90% of the one impinging onto the outer target. Finally, an attempt was made to extend the obtained results towards ITER. This simple analysis suggests that a large wall clearance and a small incidence angle of the magnetic field line, not only on the divertor target but also on ITER’s first wall, might have a crucial role in preventing wall damage during QCE discharges.

Nuclear FusionVol. 66(4)
Max Planck Institute for Plasma Physics (DE), University of Milano-Bicocca (IT)
Openalex Percentile: Top 37%
Magnetic confinement fusion research
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