Stellarator reactor: Difference between revisions
Jump to navigation
Jump to search
No edit summary |
No edit summary |
||
| Line 14: | Line 14: | ||
* The magnetic configuration can be specifically optimized to reduce transport | * The magnetic configuration can be specifically optimized to reduce transport | ||
* Nearly complete external control of the configuration increases operational robustness and lessens the need for control and feedback systems | * Nearly complete external control of the configuration increases operational robustness and lessens the need for control and feedback systems | ||
* Stellarator divertors, with long connection lengths and embedded magnetic islands, may mitigate heat loads on target plates by radiating some of the power | * Stellarator [[Divertor|divertors]], with long connection lengths and embedded magnetic islands, may mitigate heat loads on target plates by radiating some of the power | ||
== References == | == References == | ||
<references /> | <references /> | ||
Revision as of 11:51, 12 June 2010
Although the main effort of the fusion community for the development of a fusion reactor is focused on the tokamak design (ITER), design studies have been made for a fusion reactor based on the stellarator design. [1] [2] [3] [4] [5] [6]
The main advantages of the stellarator concept over the tokamak concept are:
- The density limit is 2 to 5 times higher
- Performance (beta or β) is not limited by disruptions. β values of up to 5% have been achieved
- Access to continuous operation due to the reduced amplitude or absence of net plasma current
- ELMs occur but can be controlled by selecting the magnetic configuration (iota windows or magnetic field ergodicity)
- The magnetic configuration can be specifically optimized to reduce transport
- Nearly complete external control of the configuration increases operational robustness and lessens the need for control and feedback systems
- Stellarator divertors, with long connection lengths and embedded magnetic islands, may mitigate heat loads on target plates by radiating some of the power
References
- ↑ H. Wobig, The theoretical basis of a drift-optimized stellarator reactor, Plasma Phys. Control. Fusion 35 (1993) 903-917
- ↑ J.F. Lyon and G.H. Neilson, Compact Stellarators, Journal of Fusion Energy 17, 3 (1998) 189-191
- ↑ G.H. Neilson et al, Physics issues in the design of high-beta, low-aspect-ratio stellarator experiments, Phys. Plasmas 7 (2000) 1911
- ↑ C.D. Beidler et al, Stellarator Fusion Reactors - an overview, J. Plasma Fusion Res. SERIES 5 (2002) 149-155
- ↑ H. Wobig and F. Wagner, Nuclear Energy. Chapter 7, Magnetic confinement fusion: stellarator (2005) ISBN 978-3-540-42891-6
- ↑ R.C. Wolf et al, A stellarator reactor based on the optimization criteria of Wendelstein 7-X, Fusion Engineering and Design 83, Issues 7-9 (2008) 990-996