Taming harmful bursts and heat flux in high-confinement tokamak plasmas

Hu, Q. M.; Wang, Huiqian Q.; Navarro, Marco X.; Wang, H. H.; Eldon, David; Gu, S.; Ma, Xinxing; Frerichs, Heinke; Scotti, Filippo; Wang, Liang; Wilcox, Robert S.; Wilks, Theresa M.; Bortolon, Alessandro; Ceelen, Lennard; Effenberg, Florian; Gong, X. Z.; Jia, M. N.; Kim, SangKyeun; Lasnier, C. J.; Leonard, A. W.; Li, K. D.; Logan, Nikolas C.; Ma, Q.; Maingi, Rajesh; Meng, L. Y.; Moser, Auna L.; Osborne, Thomas H.; Paz-Soldan, Carlos; Shafer, Morgan W.; Sun, Y. W.; Yang, SeongMoo; Ye, C.

doi:10.1038/s41467-025-67080-1

Title: Taming harmful bursts and heat flux in high-confinement tokamak plasmas

Journal Article · Fri Dec 05 00:00:00 UTC 2025 · Nature Communications

DOI: https://doi.org/10.1038/s41467-025-67080-1 · OSTI ID:3013433

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^[2]; Navarro, Marco X. ^[3]; Wang, H. H. ^[4];

^[2]; Gu, S. ^[4]; Ma, Xinxing ^[2]; Frerichs, Heinke ^[3]; Scotti, Filippo ^[5];

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^[6]; Wilks, Theresa M. ^[7];

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^[1]; Gong, X. Z. ^[4]; Jia, M. N. ^[4];

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^[5]; Leonard, A. W. ^[2] more »

Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
General Atomics, San Diego, CA (United States)
University of Wisconsin, Madison, WI (United States)
Chinese Academy of Sciences (CAS), Hefei (China)
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Massachusetts Institute of Technology, Cambridge, MA (United States)
DIFFER–Dutch Institute for Fundamental Energy Research, Eindhoven (Netherlands); Eindhoven University of Technology (Netherlands)
Columbia University, New York, NY (United States)

A major challenge in tokamak fusion research is first-wall erosion caused by steady heat loads and sudden energy bursts known as edge-localized modes. Divertor detachment reduces steady-state heat flux, while resonant magnetic perturbations can suppress these instabilities. However, integrating the two has been difficult because they require conflicting operating conditions. Here we demonstrate simultaneous achievement of resonant magnetic perturbations mitigated small edge-localized modes and impurity seeded partial divertor detachment in plasmas with an ITER-similar shape on the DIII-D tokamak. Experiments and simulations show that resonant magnetic perturbations facilitate detachment by redistributing particles, lowering the core density and increasing the scrape-off layer density, thereby reducing the amount of injected gas required. Cooling-gas injection eliminates the secondary heat-flux peak created by three-dimensional magnetic lobes, while edge cooling weakens the plasma response to the applied magnetic fields. These advances illustrate a viable pathway for integrating edge stability control with power exhaust in future fusion reactors.

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Research Organization:: General Atomics, San Diego, CA (United States); Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC02-09CH11466; AC05-00OR22725; AC52-07NA27344; FC02-04ER54698; SC0014264; SC0020284; SC0020357; SC0022270

OSTI ID:: 3013433

Journal Information:: Nature Communications, Journal Name: Nature Communications Journal Issue: 1 Vol. 17; ISSN 2041-1723

Publisher:: Nature Publishing GroupCopyright Statement

Country of Publication:: United States

Language:: English

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A Brief Introduction to the DIII-D Tokamak Luxon, J. L. Fusion Science and Technology, Vol. 48, Issue 2 https://doi.org/10.13182/FST05-A1042	journal	October 2005
The EIRENE and B2-EIRENE Codes Reiter, D.; Baelmans, M.; Börner, P. Fusion Science and Technology, Vol. 47, Issue 2 https://doi.org/10.13182/FST47-172	journal	February 2005
Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling Bonnin, Xavier; Dekeyser, Wouter; Pitts, Richard Plasma and Fusion Research, Vol. 11, Issue 0 https://doi.org/10.1585/pfr.11.1403102	journal	January 2016

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