Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Plasma Facing Component Characterization and Correlation With Plasma Conditions in Lithium Tokamak Experiment-β

Journal Article · · IEEE Transactions on Plasma Science
Lithium coatings in the Lithium Tokamak eXperiment (LTX) led to flat temperature profiles. The flat temperature profiles were observed along with a hot, low density edge, implying a broad, collisionless scrape-off layer (SOL). Additionally, in vacuo X-ray photoelectron spectroscopy (XPS) measurements established that lithium coatings evaporatively deposited onto high-Z plasma facing components (PFCs) became oxidized while retaining the ability to achieve good plasma performance long after lithium was applied to the PFCs. Longstanding theory predicted flat temperature profiles with low recycling walls, which was presumed to be due to hydrogen binding with elemental lithium to form lithium hydride. The presence of oxidized lithium, however, raised questions regarding the exact mechanism of hydrogen retention in LTX. To investigate these questions, the upgraded facility LTX-β includes a new sample exposure probe (SEP) for more detailed in vacuo analysis of PFC samples. The SEP is equipped with a vacuum suitcase capable of transporting samples representative of the LTX-β outer midplane PFCs to a stand-alone XPS system while maintaining pressures lower than the LTX-β base vacuum to limit the contamination between sample exposure and analysis. The low-energy resolution XPS system used in past experiments could only enable the determination of elemental percentages on the PFC sample surfaces. Because the new XPS system has higher energy resolution, it is more direct to assign chemical compounds to the measured binding energies. This capability has been confirmed by comparing XPS data from PFC test samples with measurements using a commercial high-resolution XPS system. Quartz crystal microbalances (QCMs) were used to quantify the thickness of the deposited lithium on the LTX-β PFCs. This work describes the application of the SEP to characterize the PFC surfaces using XPS and their relationship to plasma conditions.
Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC02-09CH11466; AC05-00OR22725; AC52-07NA27344; SC0019308
OSTI ID:
1883010
Alternate ID(s):
OSTI ID: 1649328
Report Number(s):
LLNL-JRNL-839007; 1058333
Journal Information:
IEEE Transactions on Plasma Science, Journal Name: IEEE Transactions on Plasma Science Journal Issue: 6 Vol. 48; ISSN 0093-3813
Publisher:
IEEECopyright Statement
Country of Publication:
United States
Language:
English

References (16)

XPS analysis of a lithium surface immersed in propylene carbonate solution containing various salts journal July 1992
An XPS study of the adsorption of oxygen and water vapor on clean lithium films journal May 1984
Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U journal April 2017
Dependence of LTX plasma performance on surface conditions as determined by in situ analysis of plasma facing components journal August 2015
Hydrogen retention in lithium and lithium oxide films journal April 2018
Effect of boronization on plasma-facing graphite surfaces and its correlation with the plasma behavior in NSTX-U journal December 2018
XPS on Li-Battery-Related Compounds: Analysis of Inorganic SEI Phases and a Methodology for Charge Correction journal August 2018
Atomic Layer Deposition and in Situ Characterization of Ultraclean Lithium Oxide and Lithium Hydroxide journal November 2014
The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment journal May 2008
High performance discharges in the Lithium Tokamak eXperiment with liquid lithium wallsa) journal May 2015
A simple vacuum suitcase for enabling plasma facing component characterization in fusion devices journal February 2020
Enhancement of Tokamak Fusion Test Reactor performance by lithium conditioning journal May 1996
The second phase of JET operation with the ITER-like wall journal April 2014
Primary Results of Lithium Coating for the Improvement of Plasma Performance in EAST journal December 2010
Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment journal July 2017
Enhanced Energy Confinement and Performance in a Low-Recycling Tokamak journal August 2006