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

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 comp...

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Published inNuclear fusion Vol. 63; no. 1; pp. 16001 - 16011
Main Authors Pan, O., Bernert, M., Lunt, T., Cavedon, M., Kurzan, B., Wiesen, S., Wischmeier, M., Stroth, U., Upgrade Team, the ASDEX
Format Journal Article
LanguageEnglish
Published IOP Publishing 01.01.2023
Subjects
power exhaust
SOLPS-ITER
X-point radiator
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Summary: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.
Bibliography:International Atomic Energy Agency
NF-105637.R1
ISSN:0029-5515
1741-4326
DOI:10.1088/1741-4326/ac9742