Aug 2016 | Research Library, Papers, Diagnostics, Experiment, Fusion Energy, Fusion Research, Fusion Science, Fusion Technology
August 2016 | R. M. Magee | Review of Scientific Instruments | Paper
In the C-2U fusion energy experiment, high power neutral beam injection creates a large fast ion population that sustains a field-reversed configuration (FRC) plasma. The diagnosis of the fast ion pressure in these high-performance plasmas is therefore critical, and the measurement of the flux of neutrons from the deuterium-deuterium (D-D) fusion reaction is well suited to the task.
Aug 2016 | Research Library, Papers, Diagnostics, Experiment, Fusion Energy, Fusion Research, Fusion Science, Fusion Technology
August 2016 | E. M. Granstedt | Review of Scientific Instruments | Paper
The C-2U device employed neutral beam injection, end-biasing, and various particle fueling tech- niques to sustain a Field-Reversed Configuration (FRC) plasma. As part of the diagnostic suite, two fast imaging instruments with radial and nearly axial plasma views were developed using a common camera platform.
Aug 2016 | Research Library, Papers, Diagnostics, Experiment, Fusion Energy, Fusion Research, Fusion Science, Fusion Technology
August 2016 | D. Osin | Review of Scientific Instruments | Paper
A dual wavelength imaging system has been developed and installed on C-2U to capture 2D images of a He jet in the Scrape-O↵ Layer (SOL) of an advanced beam-driven Field-Reversed Configuration (FRC) plasma. The system was designed to optically split two identical images and pass them through 1 nm FWHM filters.
Aug 2016 | Research Library, Papers, Diagnostics, Experiment, Fusion Energy, Fusion Research, Fusion Science, Fusion Technology
August 2016 | T. Roche | Review of Scientific Instruments | Paper
External flux conserving coils were installed onto the exterior of the C-2U confinement vessel to increase the flux confinement time of the system. The 0.5 in. stainless steel vessel wall has a skin time of ⇠5 ms. The addition of the external copper coils e↵ectively increases this time to ⇠7 ms.
Jul 2016 | Research Library, Papers, Diagnostics, Experiment, Fueling, Fusion Energy, Fusion Research, Fusion Science, Fusion Technology
July 2016 | T. Matsumoto | Review of Scientific Instruments | Paper
We have developed a compact toroid (CT) injector system for particle refueling of the advanced beam- driven C-2U field-reversed configuration (FRC) plasma. The CT injector is a magnetized coaxial plasma gun (MCPG), and the produced CT must cross the perpendicular magnetic field surrounding the FRC for the refueling of C-2U.
