National Spherical Torus Experiment
National Spherical Torus Experiment | |
---|---|
MW | |
Plasma current | 1.4 MA |
History | |
Year(s) of operation | 1999–present |
Preceded by | Tokamak Fusion Test Reactor (TFTR) |
Links | |
Website | NSTX-U official website |
The National Spherical Torus Experiment (NSTX) is a
Like other magnetic confinement fusion experiments, NSTX studies the physics principles of thermonuclear plasmas—ionized gases with sufficiently high temperatures and densities for nuclear fusion to occur—which are confined in a magnetic field.
The spherical tokamak design implemented by NSTX is an offshoot of the conventional tokamak. Proponents claim that spherical tokamaks have dramatic practical advantages over conventional tokamaks. For this reason the spherical tokamak has seen considerable interest since it was proposed in the late 1980s. However, development remains effectively one generation behind mainline tokamak efforts such as JET. Other major spherical tokamak experiments include the START and MAST at Culham in the UK.
History
1999–2012
First plasma was obtained on NSTX on Friday, February 12, 1999 at 7:06 p.m.
Magnetic fusion experiments use plasmas composed of one or more hydrogen
NSTX produced a spherical plasma with a hole through its center (a "cored apple" profile; see
Upgrade 2012–2015
The $94 million[1] NSTX-U (Upgrade)[2] was completed in 2015. It doubles the toroidal field (to 1 Tesla), plasma current (to 2 MA) and heating power. It increases the pulse duration by a factor of five.[3] To achieve this the central stack (CS) solenoid was widened,[4] and an OH coil, inner poloidal coils, and a 2nd neutral-ion beam line were added.[5] This upgrade consisted of a copper coil installation, not a superconducting coil.
Poloidal coil problem 2016 and Recovery 2016–present
The NSTX-U (Upgrade) was stopped in late 2016 just after its update, due to a failure of one its poloidal coils.[5] The NSTX had been shut down since 2012 and only returned for 10 weeks at the end of 2016 just after it was updated. The origin of this failure is partly attributed to a non-compliance of the chilled copper winding, the manufacture of which had been sub-contracted. After a diagnostic phase requiring the complete dismantling of the device and coils, evaluation of the design, and a redesign of major components including the six inner poloidal coils,[5][6] a restarting plan was adopted in March 2018, with reactivation scheduled for the end of 2020,[7] though this was later pushed back to 2022.[8] As of 2022, the restart was still delayed due to an insulation problem between the central solenoid and the coils around it.[9]
References
- ^ "NSTX-U Press Kit". Princeton Plasma Physics Lab.
- ^ "Diagram of NSTX-U changes". Archived from the original on 2021-03-23. Retrieved 2020-11-14.
- ^ The Role of the Spherical Tokamak in the U.S. Fusion Energy Sciences Program Menard, 2012
- ^ "PPPL to launch major upgrade of key fusion energy test facility". Princeton Plasma Physics Lab. Jan 2012. Archived from the original on 2020-12-20. Retrieved 2015-12-12.
- ^ a b c "Overview of the NSTX-U Recovery Project Physics and Engineering Design" (PDF). S. P. Gerhardt, et al. Archived from the original (PDF) on 2022-12-21. Retrieved 2019-09-07.
- ^ "NSTX-U recovery plan: Environmental Evaluation Notification Form" (PDF). NSTX-U recovery project. August 2017.
$65,000,000 ... * Redesign and Replace the Inner Poloidal Field (PF) Coils : The six PF- I magnet coils would be replaced with new coils or improved design: they would be mandrel-less, have no joggles, and no braze joints. * Redesign and Replace Polar Regions of NSTX-U : The top and bottom of the NSTX-U device would be redesigned with numerous design improvements. All single 0-ring seals would be replaced by double 0-rings or a metallic structure, the PF-1c vacuum interface would be made more robust, one of either the upper or lower ceramic insulators would be eliminated, and the PF-lb coil supports would be thermally isolated from the vessel. * Redesign and Replace Plasma Facing Components.
- ^ "[1st] Review of NSTX-U Recovery plans notes progress and outlines challenges" (PDF). Princeton Plasma Physics Lab. 12 Feb 2018.
- ^ Cho, Adrian (2020-02-06). "After decades of decline, the U.S. national fusion lab seeks a rebirth". Science | AAAS. Retrieved 2020-02-07.
- ^ Gerhardt, Stefan (2022-03-16). "Team Meeting 3/16/2022" (PDF). NSTX-U Team Meeting. p. 4. Retrieved 2022-10-14.
Sources
- "National Spherical Torus Experiment". Princeton Plasma Physics Laboratory. Archived from the original on 2021-03-20. Retrieved 2014-03-02. – Original source for this article was an earlier version of this page.
- "Schematic diagram of NSTX". Princeton Plasma Physics Laboratory. Retrieved 2009-08-07.
- Schematic diagram of NSTX-U Facility Upgraded Components[permanent dead link]