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Title: The Thomson Scattering System on the Lithium Tokamak eXperiment (LTX)

Abstract

The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ~ 3.4kG, IP ~ 400kA, and pulse length ~ 0.25s. The goal of LTX is to investigate tokamak plasmas that are almost entirely surrounded by a lithium-coated plasma-facing shell conformal to the last closed magnetic flux surface. Based on previous experimental results and simulation, it is expected that the low-recycling liquid lithium surfaces will result in higher temperatures at the plasma edge, flatter overall temperature profiles, centrally-peaked density profiles, and an increased confinement time. To test these predictions, the electron temperature and density profiles in LTX will be measured by a multi-point Thomson scattering system (TVTS). Initially, TS measurements will be made at up to 12 simultaneous points between the plasma center and plasma edge. Later, high resolution edge measurements will be deployed to study the lithium edge physics in greater detail. Technical challenges to implementing the TS system included limited "line of sight" access to the plasma due to the plasma-facing shell and problems associated with the presence of liquid lithium.

Authors:
Publication Date:
Research Org.:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
953701
Report Number(s):
PPPL-4339
TRN: US1004025
DOE Contract Number:  
DE-ACO2-76CHO3073
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CONFINEMENT TIME; ELECTRON TEMPERATURE; LITHIUM; MAGNETIC FLUX; PLASMA; RESOLUTION; SIMULATION; THOMSON SCATTERING; TOKAMAK DEVICES; Tokamaks; Thomson Scattering

Citation Formats

T. Strickler, R. Majeski, R. Kaita, B. LeBlanc. The Thomson Scattering System on the Lithium Tokamak eXperiment (LTX). United States: N. p., 2008. Web. doi:10.2172/953701.
T. Strickler, R. Majeski, R. Kaita, B. LeBlanc. The Thomson Scattering System on the Lithium Tokamak eXperiment (LTX). United States. doi:10.2172/953701.
T. Strickler, R. Majeski, R. Kaita, B. LeBlanc. Thu . "The Thomson Scattering System on the Lithium Tokamak eXperiment (LTX)". United States. doi:10.2172/953701. https://www.osti.gov/servlets/purl/953701.
@article{osti_953701,
title = {The Thomson Scattering System on the Lithium Tokamak eXperiment (LTX)},
author = {T. Strickler, R. Majeski, R. Kaita, B. LeBlanc},
abstractNote = {The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ~ 3.4kG, IP ~ 400kA, and pulse length ~ 0.25s. The goal of LTX is to investigate tokamak plasmas that are almost entirely surrounded by a lithium-coated plasma-facing shell conformal to the last closed magnetic flux surface. Based on previous experimental results and simulation, it is expected that the low-recycling liquid lithium surfaces will result in higher temperatures at the plasma edge, flatter overall temperature profiles, centrally-peaked density profiles, and an increased confinement time. To test these predictions, the electron temperature and density profiles in LTX will be measured by a multi-point Thomson scattering system (TVTS). Initially, TS measurements will be made at up to 12 simultaneous points between the plasma center and plasma edge. Later, high resolution edge measurements will be deployed to study the lithium edge physics in greater detail. Technical challenges to implementing the TS system included limited "line of sight" access to the plasma due to the plasma-facing shell and problems associated with the presence of liquid lithium.},
doi = {10.2172/953701},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jul 31 00:00:00 EDT 2008},
month = {Thu Jul 31 00:00:00 EDT 2008}
}

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