Mitigation of plasma–wall interactions with low-Z powders in DIII-D high confinement plasmas

Effenberg, F.; Bortolon, A.; Casali, L.; Nazikian, R.; Bykov, I.; Scotti, F.; Wang, H. Q.; Fenstermacher, M. E.; Lunsford, R.; Nagy, A.; Grierson, B. A.; Laggner, F. M.; Maingi, R.

doi:10.1088/1741-4326/ac899d

Mitigation of plasma–wall interactions with low-Z powders in DIII-D high confinement plasmas

Journal Article · Wed Aug 31 00:00:00 EDT 2022 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/ac899d· OSTI ID:1884557

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Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); General Atomics, Magnetic Fusion Energy, DIII-D
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Univ. of Tennessee, Knoxville, TN (United States)
General Atomics, San Diego, CA (United States)
General Atomics, San Diego, CA (United States); Univ. of California San Diego, La Jolla, CA (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Experiments with low-Z powder injection in DIII-D high confinement discharges demonstrated increased divertor dissipation and detachment while maintaining good core energy confinement. Lithium (Li), boron (B), and boron nitride (BN) powders were injected in H-mode plasmas (I_p = 1 MA, B_t = 2 T, P_NB = 6 MW, < n_e > = 3.6–5.0 · 10¹⁹ m^–3) into the upper small-angle slot divertor for 2 s intervals at constant rates of 3–204 mg s^–1. The multi-species BN powders at a rate of 54 mg s^–1 showed the most substantial increase in divertor neutral compression by more than an order of magnitude and lasting detachment with minor degradation of the stored magnetic energy W_mhd by 5%. Rates of 204 mg s^–1 of boron nitride powder further reduce edge localized mode-fluxes on the divertor but also cause a drop in confinement performance by 24% due to the onset of an n = 2 tearing mode. The application of powders also showed a substantial improvement of wall conditions manifesting in reduced wall fueling source and intrinsic carbon and oxygen content in response to the cumulative injection of non-recycling materials. Furthermore, the results suggest that low-Z powder injection, including mixed element compounds, is a promising new core-edge compatible technique that simultaneously enables divertor detachment and improves wall conditions during high confinement operation.

View Accepted Manuscript (DOE)

Research Organization:: General Atomics, San Diego, CA (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Contributing Organization:: DIII-D Team

Grant/Contract Number:: AC02-09CH11466; AC52-07NA27344; FC02-04ER54698; FG02-07ER54917

OSTI ID:: 1884557

Alternate ID(s):: OSTI ID: 2282407

Report Number(s):: LLNL--JRNL-857628

Journal Information:: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 10 Vol. 62; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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Mitigation of plasma–wall interactions with low-Z powders in DIII-D high confinement plasmas

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