The X-point radiator (XPR) is an attractive scenario that may contribute to solving the power exhaust problem in future fusion devices. The 2D transport code SOLPS-ITER was applied to reproduce the experimentally measured plasma condition with an XPR in the ASDEX Upgrade tokamak and to compare with a reduced model. Neutrals penetrating from the adjoining cold divertor region and the large connection length near the X-point play an important role in initiating an XPR. However, once such a radiator is created, it persists even if the fueling and impurity seeding rates were reduced. The redistribution of plasma density and radiation near the X-point caused by fluid drifts at the XPR was studied in the simulation.

Pan, O., Bernert, M., Lunt, T., Cavedon, M., Kurzan, B., Wiesen, S., et al. (2023). SOLPS-ITER simulations of an X-point radiator in the ASDEX Upgrade tokamak. NUCLEAR FUSION, 63(1 (January 2023)) [10.1088/1741-4326/ac9742].

SOLPS-ITER simulations of an X-point radiator in the ASDEX Upgrade tokamak

Cavedon M.;
2023

Abstract

The X-point radiator (XPR) is an attractive scenario that may contribute to solving the power exhaust problem in future fusion devices. The 2D transport code SOLPS-ITER was applied to reproduce the experimentally measured plasma condition with an XPR in the ASDEX Upgrade tokamak and to compare with a reduced model. Neutrals penetrating from the adjoining cold divertor region and the large connection length near the X-point play an important role in initiating an XPR. However, once such a radiator is created, it persists even if the fueling and impurity seeding rates were reduced. The redistribution of plasma density and radiation near the X-point caused by fluid drifts at the XPR was studied in the simulation.
Articolo in rivista - Articolo scientifico
power exhaust; SOLPS-ITER; X-point radiator;
English
28-nov-2022
2023
63
1 (January 2023)
016001
open
Pan, O., Bernert, M., Lunt, T., Cavedon, M., Kurzan, B., Wiesen, S., et al. (2023). SOLPS-ITER simulations of an X-point radiator in the ASDEX Upgrade tokamak. NUCLEAR FUSION, 63(1 (January 2023)) [10.1088/1741-4326/ac9742].
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/10281/401006
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