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The Lithium Tokamak EXperiment (LTX): Status And Plans.pdf

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Preview of The Lithium Tokamak eXperiment (LTX): Status and Plans
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Summary

The Lithium Tokamak eXperiment (LTX) is a novel toroidal device designed to explore a new plasma regime with flat temperature profiles, achieved through a fully non-recycling plasma-facing component (PFC). LTX, a spherical tokamak, aims to operate with specific parameters: R=40 cm, a=26 cm, Bt=3.4 kG, Ip=400 kA, Te=1 keV, and Ti=200 eV for discharges exceeding 100 ms.

The device features a copper shell divided into four segments, each with a stainless steel liner coated in up to 100 nm of lithium. To maintain the lithium's chemical activity, the shell temperature will be elevated above the lithium melting point. Initial experiments will utilize a toroidal "pool" of liquid lithium in the lower half of the shell, mirroring results from the Current Drive eXperiment - Upgrade (CDX-U).

Assembly of LTX is complete, and preparations for plasma operations are underway. Supported by US DOE contract #DE-AC02-76CH-03073, this project marks a significant step in understanding and harnessing the potential of non-recycling PFCs in tokamak plasmas.

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Description

The Lithium Tokamak eXperiment (LTX) aims to explore a new plasma regime with flat temperature profiles by employing a fully non-recycling wall, utilizing a spherical tokamak design with specific parameters for extended discharges. The experiment involves vapor depositing a lithium layer on a copper and stainless steel shell.

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  • File Format: PDF
  • File Size: 16 KB
  • Pages: 1
  • Language: EN
  • Total Downloads: 24
  • Last Updated: 3 weeks ago

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Lithium guideLithium tutorialTokamak guideTokamak tutorialeXperiment guideeXperiment tutorial(LTX): guide(LTX): tutorialStatus guideStatus tutorialPlans guidePlans tutorial

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