Abstract Details
Abstracts
Author: Chris Hansen
Requested Type: Poster
Submitted: 2019-02-22 11:50:30
Co-authors: P. Hughes, D. Boyle, D. Majeski
Contact Info:
University of Washington
AERB 120, University of Washin
Seattle, 98195
United States
Abstract Text:
The Lithium Tokamak eXperiment (LTX) research program focuses on modifications to the core equilibrium and scrape-off layer (SOL) caused by metallic low-recycling lithium plasma facing surfaces [1]. As part of the recent upgrade (LTX-β), a neutral beam injection system has been added to provide heating and core fueling, where previously only Ohmic heating and edge puff fueling were available. Analyzing the effect of lithium coated walls on plasma transport and equilibria requires accurate reconstruction of the plasma position, shape and equilibrium profiles. Currently, PSI-Tri is the only available tool that provides reconstructions of plasma equilibria in LTX-β that match all available diagnostics within experimental error bars [2]. Additionally, PSI-Tri reconstructions provide estimates of eddy current induced 3D error fields, which can be important in core transport, SOL, and other analysis. Code and diagnostic improvements in support of the LTX-β program include: 1) Local magnetic diagnostics designed to better measure 3D fields generated by first wall eddy currents, 2) refinement of the 3D eddy current model used in reconstructions and 3) extension of the PSI-Tri equilibrium model to include toroidal plasma rotation. Progress and results for initial operation of LTX-β will be presented. Work supported by DOE.
[1]- D. Boyle et al., Phys. Rev. Lett. 119, 015001 (2017)
[2]- C. Hansen et al., Phys. Plasmas 24, 086035 (2017)
Comments:
