Stellarator reactor - Revision history

Admin at 10:38, 26 January 2023

2023-01-26T10:38:45Z

← Older revision		Revision as of 12:38, 26 January 2023
Line 4:		Line 4:
	<ref>G.H. Neilson et al, ''Physics issues in the design of high-beta, low-aspect-ratio stellarator experiments'', [[doi:10.1063/1.874015\|Phys. Plasmas '''7''' (2000) 1911]]</ref>		<ref>G.H. Neilson et al, ''Physics issues in the design of high-beta, low-aspect-ratio stellarator experiments'', [[doi:10.1063/1.874015\|Phys. Plasmas '''7''' (2000) 1911]]</ref>
	<ref>C.D. Beidler et al, ''Stellarator Fusion Reactors - an overview'', [http://www.jspf.or.jp/JPFRS/PDF/Vol5/jpfrs2002_05-149.pdf J. Plasma Fusion Res. SERIES '''5''' (2002) 149-155]</ref>		<ref>C.D. Beidler et al, ''Stellarator Fusion Reactors - an overview'', [http://www.jspf.or.jp/JPFRS/PDF/Vol5/jpfrs2002_05-149.pdf J. Plasma Fusion Res. SERIES '''5''' (2002) 149-155]</ref>
	<ref>H. Wobig and F. Wagner, [[doi:10857629_17\|''Nuclear Energy. Chapter 7, Magnetic confinement fusion: stellarator'' (2005)]] ISBN 978-3-540-42891-6</ref>		<ref>H. Wobig and F. Wagner, [[doi:10857629_17\|''Nuclear Energy. Chapter 7, Magnetic confinement fusion: stellarator'' (2005)]] {{ISBN\|978-3-540-42891-6}}</ref>
	<ref>R.C. Wolf et al, ''A stellarator reactor based on the optimization criteria of Wendelstein 7-X'', [[doi:10.1016/j.fusengdes.2008.05.008\|Fusion Engineering and Design '''83''', Issues 7-9 (2008) 990-996]]</ref>		<ref>R.C. Wolf et al, ''A stellarator reactor based on the optimization criteria of Wendelstein 7-X'', [[doi:10.1016/j.fusengdes.2008.05.008\|Fusion Engineering and Design '''83''', Issues 7-9 (2008) 990-996]]</ref>

Admin: Updated reference links

2018-04-03T13:48:03Z

Updated reference links

← Older revision		Revision as of 15:48, 3 April 2018
Line 1:		Line 1:
	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.		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>H. Wobig, ''The theoretical basis of a drift-optimized stellarator reactor'', [[doi:10.1088/0741-3335/35/8/001\|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>J.F. Lyon and G.H. Neilson, '' Compact Stellarators'', [[doi:10.1023/A:1021841825478\|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>G.H. Neilson et al, ''Physics issues in the design of high-beta, low-aspect-ratio stellarator experiments'', [[doi:10.1063/1.874015\|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>C.D. Beidler et al, ''Stellarator Fusion Reactors - an overview'', [http://www.jspf.or.jp/JPFRS/PDF/Vol5/jpfrs2002_05-149.pdf 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>H. Wobig and F. Wagner, [[doi:10857629_17\|''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>		<ref>R.C. Wolf et al, ''A stellarator reactor based on the optimization criteria of Wendelstein 7-X'', [[doi:10.1016/j.fusengdes.2008.05.008\|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 main advantages of the stellarator concept over the tokamak concept are:

Admin: Reverted edits by 62.39.3.10 (Talk) to last revision by Admin

2011-05-19T05:18:54Z

Reverted edits by 62.39.3.10 (Talk) to last revision by Admin

← Older revision		Revision as of 07:18, 19 May 2011
Line 1:		Line 1:
	~~In awe~~ of ~~that answer! Relaly cool!~~		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 ==
			<references />

62.39.3.10: TFixHZYuxOZrrTGxGf

2011-05-18T19:46:25Z

TFixHZYuxOZrrTGxGf

← Older revision		Revision as of 21:46, 18 May 2011
Line 1:		Line 1:
	~~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.		In awe of that answer! Relaly cool!
	~~<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 ==~~
	~~<references />~~

Admin: Reverted edits by 118.22.234.149 (Talk) to last revision by Admin

2011-05-18T17:29:03Z

Reverted edits by 118.22.234.149 (Talk) to last revision by Admin

← Older revision		Revision as of 19:29, 18 May 2011
Line 1:		Line 1:
	~~Never seen~~ a ~~beettr post! ICOCBW~~		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 ==
			<references />

118.22.234.149: Undo revision 1860 by Admin (Talk)

2011-05-18T09:39:02Z

Undo revision 1860 by Admin (Talk)

← Older revision		Revision as of 11:39, 18 May 2011
Line 1:		Line 1:
	~~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.~~		Never seen a beettr post! ICOCBW
	~~<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 ==~~
	~~<references />~~

Admin at 10:51, 12 June 2010

2010-06-12T10:51:04Z

← Older revision		Revision as of 12:51, 12 June 2010
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 />

Admin at 10:42, 23 October 2009

2009-10-23T10:42:48Z

← Older revision		Revision as of 12:42, 23 October 2009
Line 1:		Line 1:
	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\|stellarator]] design.		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/10.1088/0741-3335/35/8/001 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://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>

Admin at 18:07, 22 October 2009

2009-10-22T18:07:14Z

← Older revision		Revision as of 20:07, 22 October 2009
Line 1:		Line 1:
	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.		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\|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/10.1088/0741-3335/35/8/001 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://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>

Admin at 18:48, 9 September 2009

2009-09-09T18:48:53Z

← Older revision		Revision as of 20:48, 9 September 2009
Line 4:		Line 4:
	<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://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://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>		<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>