The Impact Of Lithium Wall Coatings On NSTX Discharges And The Engineering Of The Lithium Tokamak eXperiment (LTX)

doi:10.2172/981656

Title: The Impact Of Lithium Wall Coatings On NSTX Discharges And The Engineering Of The Lithium Tokamak eXperiment (LTX)

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Abstract

Recent experiments on the National Spherical Torus eXperiment (NSTX) have shown the benefits of solid lithium coatings on carbon PFC's to diverted plasma performance, in both Land H- mode confinement regimes. Better particle control, with decreased inductive flux consumption, and increased electron temperature, ion temperature, energy confinement time, and DD neutron rate were observed. Successive increases in lithium coverage resulted in the complete suppression of ELM activity in H-mode discharges. A liquid lithium divertor (LLD), which will employ the porous molybdenum surface developed for the LTX shell, is being installed on NSTX for the 2010 run period, and will provide comparisons between liquid walls in the Lithium Tokamak eXperiment (LTX) and liquid divertor targets in NSTX. LTX, which recently began operations at the Princeton Plasma Physics Laboratory, is the world's first confinement experiment with full liquid metal plasma-facing components (PFCs). All materials and construction techniques in LTX are compatible with liquid lithium. LTX employs an inner, heated, stainless steel-faced liner or shell, which will be lithium-coated. In order to ensure that lithium adheres to the shell, it is designed to operate at up to 500 - 600 oC to promote wetting of the stainless by the lithium, providing the firstmore »« less

Authors:: R. Majeski, H. Kugel and R. Kaita

Publication Date:: Thu Mar 18 00:00:00 EDT 2010

Research Org.:: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Org.:: USDOE Office of Science (SC)

OSTI Identifier:: 981656

Report Number(s):: PPPL-4505
TRN: US1003880

DOE Contract Number:: DE-ACO2-09CH11466

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CARBON; COATINGS; CONFINEMENT; CONFINEMENT TIME; CONSTRUCTION; DIVERTORS; ELECTRON TEMPERATURE; ION TEMPERATURE; LINERS; LIQUID METALS; LITHIUM; MOLYBDENUM; NEUTRONS; PERFORMANCE; PHYSICS; PLASMA; TARGETS; Spherical Tokamak, Spherical Torus, Plasma wall interaction

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                    R. Majeski, H. Kugel and R. Kaita. The Impact Of Lithium Wall Coatings On NSTX Discharges And The Engineering Of The Lithium Tokamak eXperiment (LTX).  United States: N. p., 2010. 
        Web.  doi:10.2172/981656.

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                    R. Majeski, H. Kugel and R. Kaita. The Impact Of Lithium Wall Coatings On NSTX Discharges And The Engineering Of The Lithium Tokamak eXperiment (LTX).  United States.  https://doi.org/10.2172/981656

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                    R. Majeski, H. Kugel and R. Kaita. 2010.  
        "The Impact Of Lithium Wall Coatings On NSTX Discharges And The Engineering Of The Lithium Tokamak eXperiment (LTX)".  United States.  https://doi.org/10.2172/981656.  https://www.osti.gov/servlets/purl/981656.

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@article{osti_981656,

  title        = {The Impact Of Lithium Wall Coatings On NSTX Discharges And The Engineering Of The Lithium Tokamak eXperiment (LTX)},

  author       = {R. Majeski, H. Kugel and R. Kaita},

  abstractNote = {Recent experiments on the National Spherical Torus eXperiment (NSTX) have shown the benefits of solid lithium coatings on carbon PFC's to diverted plasma performance, in both Land H- mode confinement regimes. Better particle control, with decreased inductive flux consumption, and increased electron temperature, ion temperature, energy confinement time, and DD neutron rate were observed. Successive increases in lithium coverage resulted in the complete suppression of ELM activity in H-mode discharges. A liquid lithium divertor (LLD), which will employ the porous molybdenum surface developed for the LTX shell, is being installed on NSTX for the 2010 run period, and will provide comparisons between liquid walls in the Lithium Tokamak eXperiment (LTX) and liquid divertor targets in NSTX. LTX, which recently began operations at the Princeton Plasma Physics Laboratory, is the world's first confinement experiment with full liquid metal plasma-facing components (PFCs). All materials and construction techniques in LTX are compatible with liquid lithium. LTX employs an inner, heated, stainless steel-faced liner or shell, which will be lithium-coated. In order to ensure that lithium adheres to the shell, it is designed to operate at up to 500 - 600 oC to promote wetting of the stainless by the lithium, providing the first hot wall in a tokamak to operate at reactor-relevant temperatures. The engineering of LTX will be discussed.},

  doi          = {10.2172/981656},

  url          = {https://www.osti.gov/biblio/981656},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Thu Mar 18 00:00:00 EDT 2010},

  month        = {Thu Mar 18 00:00:00 EDT 2010}

}

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