Radiation-front position control with scenario adjustments during the first tungsten divertor operation on KSTAR
Abstract This study reports the first experimental demonstration of a radiation front-based detachment control system during the initial tungsten divertor campaign in KSTAR. The system employs real-time infrared video bolometry with tomographic reconstruction to track the inboard radiation-front position, which served as a feedback variable for impurity seeding. In a baseline scenario without pre-D 2 fueling, tungsten accumulation triggered core radiation surges and repetitive H–L back transitions. In contrast, with pre-D 2 fueling, detachment was stabilized by maintaining higher edge-localized mode frequency, suppressing core tungsten buildup, and reducing sputtering, thereby enabling sustained feedback control. The suitability of the inboard front position as a detachment control metric was confirmed by its correlation with the degree of detachment: with D 2 fueling the relation exhibited a broad hysteresis loop characteristic of momentum-loss-dominated detachment, whereas with N 2 fueling, it became narrow and nearly vertical, consistent with radiation-loss-dominated pinning. These results provide a proof-of-principle for radiation-front-based detachment control, demonstrating its viability as a control approach. At the same time, these results clarify that the detachment outcomes were further conditioned by impurity transport characteristics of tungsten divertor operation in KSTAR, providing guidance for future scenario optimization and controller development in tungsten devices.
Authors
- Ricardo Shousha (ORCID: https://orcid.org/0000-0003-1498-8980)
- Yoon Seong Han
- S.H. Hahn (ORCID: https://orcid.org/0000-0001-8115-9248)
- Azarakhsh Jalalvand (ORCID: https://orcid.org/0000-0001-8739-1793)
- Junghoo Hwang
- Suhong Kim (ORCID: https://orcid.org/0000-0002-2315-6636)
- Jae-Sun Park
- CheolSik Byun
- Boseong Kim
- Egemen Kolemen
- Youngho Lee
- H.H. Lee
- Seungtae Oh
Institutions
- Oak Ridge National Laboratory (US)
- Korea Advanced Institute of Science and Technology (KR)
- Princeton University (US)
- Princeton Plasma Physics Laboratory (US)
- Korea Institute of Fusion Energy (KR)
Publication Details
- Journal
- Nuclear Fusion
- Published
- 2026-03-04
- DOI
- https://doi.org/10.1088/1741-4326/ae4d24
- Primary Topic
- Fusion materials and technologies
- Type
- article
- Field-Weighted Citation Impact
- 0.00
Funders
- U.S. Department of Energy