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Although the main effort of the fusion community for the development of a fusion reactor is focused on the [[Tokamak|tokamak]] design ([[ITER]]), design studies have been made for a fusion reactor based on the [[Stellarator|stellarator]] design. | |||
<ref>[http://dx.doi.org/10.1088/0741-3335/35/8/001 H. Wobig, ''The theoretical basis of a drift-optimized stellarator reactor'', Plasma Phys. Control. Fusion '''35''' (1993) 903-917]</ref> | |||
<ref>[http://dx.doi.org/10.1023/A:1021841825478 J.F. Lyon and G.H. Neilson, '' Compact Stellarators'', Journal of Fusion Energy '''17''', 3 (1998) 189-191]</ref> | |||
<ref>[http://link.aip.org/link/?PHPAEN/7/1911/1 G.H. Neilson et al, ''Physics issues in the design of high-beta, low-aspect-ratio stellarator experiments'', Phys. Plasmas '''7''' (2000) 1911]</ref> | |||
<ref>[http://www.jspf.or.jp/JPFRS/PDF/Vol5/jpfrs2002_05-149.pdf C.D. Beidler et al, ''Stellarator Fusion Reactors - an overview'', J. Plasma Fusion Res. SERIES '''5''' (2002) 149-155]</ref> | |||
<ref>[http://dx.doi.org/10.1007/10857629_17 H. Wobig and F. Wagner, ''Nuclear Energy. Chapter 7, Magnetic confinement fusion: stellarator'' (2005)] ISBN 978-3-540-42891-6</ref> | |||
<ref>[http://dx.doi.org/10.1016/j.fusengdes.2008.05.008 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]</ref> | |||
The main advantages of the stellarator concept over the tokamak concept are: | |||
* The [[Greenwald limit|density limit]] is 2 to 5 times higher | |||
* Performance ([[Beta|beta]] or β) is not limited by [[Disruption|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 | |||
* [[Edge Localized Modes|ELMs]] occur but can be controlled by selecting the magnetic configuration ([[Magnetic shear|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 [[Divertor|divertors]], with long connection lengths and embedded magnetic islands, may mitigate heat loads on target plates by radiating some of the power | |||
== References == | |||
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