Some aspects on alternative lines of magnetic confinement
Description
Facing the year 2000, some proposals for a balanced strategy of fusion research are given in this paper. Fusion research by the world community has made substantial progress, and it is now possible to build an experimental test reactor based on the tokamak confinement principle, in the form of a global commitment such as the ITER/NET project. Nevertheless further investigations are needed before the practical use of fusion energy becomes a reality. With regard to this, and to the time gap formed by the planning and construction period of ITER/NET, continued activities have to take place at the national laboratories, to preserve the quality of plasma physical research and the competence of fusion scientists and engineers, as well as to guarantee research on alternative lines aiming at an improved reactor concept. Some aspects are given in this context on the desired properties of an optimal fusion reactor, including a high plasma beta value, a minimized imposed toroidal magnetic field, controlled or non-existent disruptions, steady-state operation, minimized plasma-wall interaction, and the absence both of a stabilizing conducting wall and of active feedback systems. (au)
Availability note (English)
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22057674.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- TRITA-PFU--91-04
INIS
- Country of Publication
- Sweden
- Country of Input or Organization
- Sweden
- INIS RN
- 22057674
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- FEEDBACK; HIGH-BETA PLASMA; ITER TOKAMAK; MAGNETIC CONFINEMENT; PLANNING; REVERSE-FIELD PINCH; STEADY-STATE FUSION REACTORS; STELLARATORS; THERMONUCLEAR REACTORS; TOROIDAL PINCH DEVICES; WALL EFFECTS
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; PINCH DEVICES; PINCH EFFECT; PLASMA; PLASMA CONFINEMENT; THERMONUCLEAR DEVICES; TOKAMAK DEVICES