Oxidation of lithium plasma facing components and its effect on plasma performance in the lithium tokamak experiment-β

Maan, A.; Boyle, D. P.; Kaita, R.; Ostrowski, E. T.; Donovan, D. C.; Majeski, R. P.; Koel, B. E.; Biewer, T. M.; Hughes, P. E.; Hansen, C.; Kubota, S.; Soukhanovskii, V.

doi:10.1088/1361-6587/abcd0f

Oxidation of lithium plasma facing components and its effect on plasma performance in the lithium tokamak experiment-β

Journal Article · Wed Dec 16 00:00:00 EST 2020 · Plasma Physics and Controlled Fusion

DOI:https://doi.org/10.1088/1361-6587/abcd0f· OSTI ID:1787975

^[1]; ^[1]; Kaita, R. ^[1]; ^[2]; Donovan, D. C. ^[3]; Majeski, R. P. ^[1]; Koel, B. E. ^[2]; Biewer, T. M. ^[4]; ^[1]; ^[5]; Kubota, S. ^[6]; ^[7]

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Princeton Univ., NJ (United States). Chemical and Biological Engineering
Univ. of Tennessee, Knoxville, TN (United States). Nuclear Engineering
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Washington, Seattle, WA (United States). Aeronautics and Astronautics
Univ. of California, Los Angeles, CA (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

The characteristics of lithium-coated plasma-facing components (PFCs) have been correlated with plasma performance on the lithium tokamak experiment-β (LTX-β). Previous experiments on LTX showed that the application of lithium to PFCs was needed to achieve higher performance discharges with flat electron temperature profiles and high edge temperatures. Samples that match the LTX-β PFCs were exposed to plasmas before and after PFCs were coated with lithium and transferred under vacuum to a surface analysis station. Measurements using x-ray photoelectron spectroscopy (XPS) revealed that the primary surface constituent was lithium oxide. Earlier XPS analysis of lithium-coated PFCs on LTX was only able to show the presence of surface oxygen. The new XPS data from LTX-β have sufficient resolution to clearly identify lithium compounds for the first time, and enable them to be correlated with how lithium-coated PFCs can reduce impurities and retain hydrogen to reduce recycling.

View Accepted Manuscript (DOE)

Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Oakland Operations Office, Oakland, CA (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Nuclear Physics (NP)

Grant/Contract Number:: AC02-09CH11466; AC05-00OR22725; AC52-07NA27344

OSTI ID:: 1787975

Alternate ID(s):: OSTI ID: 1806444

Report Number(s):: LLNL-JRNL--823590

Journal Information:: Plasma Physics and Controlled Fusion, Journal Name: Plasma Physics and Controlled Fusion Journal Issue: 2 Vol. 63; ISSN 0741-3335

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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Oxidation of lithium plasma facing components and its effect on plasma performance in the lithium tokamak experiment-β

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