Model C stellarator
| Device type | Stellarator |
|---|---|
| Location | Princeton, New Jersey, United States |
| Affiliation | Princeton Plasma Physics Laboratory |
| Technical specifications | |
| Minor radius | 5–7.5 cm (2.0–3.0 in) |
| Magnetic field | 3.5 T (35,000 G) |
| History | |
| Date(s) of construction | 1961 |
| Year(s) of operation | 1962–1969 |
| Preceded by | Model A/B stellarators[1] |
| Succeeded by | Symmetric Tokamak (ST) |
The Model C stellarator was the first large-scale
USSR's T-3 tokamak
was reaching 1000 eV, the Model C was converted to the Symmetrical Tokamak, and stellarator development at PPPL ended.
Design parameters
The Model C had a racetrack shape. The total circumference of the magnetic axis was 12 m[2]. The plasma could have a 5-7.5 cm minor radius. Magnetic coils could produce a toroidal field (along the tube) of 35,000 Gauss.[1] It was only capable of pulsed operation.
It had a
ion cyclotron resonance heating
(ICRH).
It had helical windings on the curved sections.
Results
An average ion temperature of 400 eV was reached in 1969.
History
Construction funding/approval was announced in April 1957 with the design based on Katherine Weimer's efforts in fundamental research.[3][4]
It started operating March 1962.[5]
The Model C was reconfigured as a tokamak in 1969,[1] becoming the Symmetric Tokamak (ST).[6]
References
- ^ a b c d Stix, T. H. (1998). "Highlights in early stellarator research at Princeton" (PDF). J. Plasma Fusion Res. 1: 3–8.
- ISSN 0029-5515.
- ^ Princeton Alumni Weekly, Volume 57. April 19. p9
- ISSN 0031-9228.
- ^ See 1962
- ^ See 1969,1970
Further reading
- Experiments on the Model C stellarator. S. Yoshikawa and T.H. Stix
- A CONCEPTUAL DESIGN OF THE MODEL C STELLARATOR. 1956 Says 9" vacuum tube, but 150 ft long seems unlikely. 150,000 kW peak of pulsed power to the magnets.
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