Secondary Electron Emission Detectors for Neutral Beam Characterization on C-2W

April 2018 | HTPD2018 | Poster

Heating, current drive, and partial fueling from neutral beam injection are essential to sustainment of C-2W field- reversed configuration (FRC) plasmas. C-2W has eight 2.1 MW neutral beams (total of 16.8 MW), capable of providing an elliptically-shaped beam of 15 keV hydrogen neutrals for 30 ms.

Jet Outflow and Open Field Line Measurements on the C-2W Advanced Beam-Driven Field-Reversed Configuration Plasma Experiment

April 2018 | HTPD2018 | Poster

Accurate operation and high performance of the open field line plasma surrounding the Field Reversed Configuration (FRC) is crucial to achieving the goals of successful temperature ramp up and confinement improvement on C-2W.

Development of a three-wave far-infrared laser interferometry and polarimetry diagnostics for the C-2W FRC Experiment

April 2018 | HTPD2018 | Poster

C-2W field-reversed configuration (FRC) experiments [1] are focused to resolve major physics issues facing the future of FRC devices. To achieve these goals, it is essential to measure the plasma equilibrium dynamics and monitor plasma fluctuations.

Design and Characterization of High Repetition Rate Lasers and Collection Optics for Thomson Scattering Diagnostics on C-2W

April 2018 | HTPD2018 | Poster

A new Thomson scattering (TS) system is being constructed on C-2W for obtaining electron temperature and density profiles with high temporal and spatial resolution. Validating the performance of the TS’s custom designed system components is crucial to obtaining reliable Te and ne profiles of C-2W’s plasma.

Design of a Custom Insertable Probe Platform for Measurements of C-2W Inner Divertor Plasma Parameters

April 2018 | HTPD2018 | Poster

A custom motor controlled probe system has been designed to make spatially resolved measurements of temperature, density, flow, and plasma potential in the C-2W inner divertors. Measurements in the inner divertors, which have a radius of 1.7 m and are located on either end of the confinement vessel, are critical in order to gauge exactly how local settings affect the plasma conditions, confinement, and stability in the FRC core.