March 2019 Notable
A run campaign compelled by an FES-designated Lab Notable requiring the LTX project to:
Conduct energy confinement studies of neutral beam-heated and fueled plasmas with very low recycling walls in the recently upgraded Lithium Tokamak eXperiment (LTX)-β. Generate plasmas that simultaneously achieve 0.3 T of toroidal magnetic field and 0.5 MW of injected neutral beam power, while all plasma-facing components are coated with lithium. Submit a report documenting the results of these experiments to DOE by March 31, 2019 (Objective 1.1).
The campaign began XXX, and concluded on XXX, culminating in the LTX-β March 2019 Notable Report.
Following Studies
Neutral Beam Coupling and Fast Ion Loss
Began late in summer of 2019 after mode analysis algorithms for the toroidal array were implemented and tested on several shots from the Notable run campaign. It was discovered that on certain shots, a rotating n=1 structure appeared shortly before the time of beam injection on both NBI and non-NBI discharges, and that neutral beam injection correlated strongly with a change in the rotation of these modes. The rotation was observed to be in the counter-beam, counter-IP (+φ) direction, which indicated a torque due to a radial current generated by fast ion losses.
In particular, the NBI and non-NBI shots with the clearest mode dynamics from this data set are:
NBI: 100981 and 100985
Non-NBI: 100988 and 100989
Related Pages
Neutral Beam
Lithium application
Toroidal array
Automated analysis
Past Experiments
LTX/LTX-β: 2015 Flat Te study | March 2019 Notable | January 2020 Notable
Supporting: Shell Motion Testing | TF Coil Inductive Hipot Testing
Calibrations: Mirnov calibration | Integrator calibration| Coil current monitor testing
