Disruption - Revision history

Admin at 13:04, 5 June 2014

2014-06-05T13:04:31Z

← Older revision		Revision as of 15:04, 5 June 2014
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	<ref>G. A. Rattá, J. Vega, A. Murari, M. Johnson, and JET-EFDA Contributors, ''Feature extraction for improved disruption prediction analysis at JET'',[[doi:10.1063/1.2965020\|Rev. Sci. Instrum. '''79''' (2008) 10F328]]</ref>		<ref>G. A. Rattá, J. Vega, A. Murari, M. Johnson, and JET-EFDA Contributors, ''Feature extraction for improved disruption prediction analysis at JET'',[[doi:10.1063/1.2965020\|Rev. Sci. Instrum. '''79''' (2008) 10F328]]</ref>
	<ref>G.A. Rattá, J. Vega, A. Murari, G. Vagliasindi, M.F. Johnson, P.C. de Vries and JET EFDA Contributors, ''An advanced disruption predictor for JET tested in a simulated real-time environment'', [[doi:10.1088/0029-5515/50/2/025005\|Nucl. Fusion '''50''' (2010) 025005]]</ref>		<ref>G.A. Rattá, J. Vega, A. Murari, G. Vagliasindi, M.F. Johnson, P.C. de Vries and JET EFDA Contributors, ''An advanced disruption predictor for JET tested in a simulated real-time environment'', [[doi:10.1088/0029-5515/50/2/025005\|Nucl. Fusion '''50''' (2010) 025005]]</ref>
	<ref>G.A. Rattá, J. Vega, A. Murari, JET-EFDA Contributors, ''Improved feature selection based on genetic algorithms for real time disruption prediction on JET [[doi:10.1016/j.fusengdes.2012.07.002\|Fusion Engineering and Design '''87''' (2012) 1670–1678]]</ref>		<ref>G.A. Rattá, J. Vega, A. Murari, JET-EFDA Contributors, ''Improved feature selection based on genetic algorithms for real time disruption prediction on JET'' [[doi:10.1016/j.fusengdes.2012.07.002\|Fusion Engineering and Design '''87''' (2012) 1670–1678]]</ref>

	== References ==		== References ==
	<references />		<references />

Admin at 12:57, 5 June 2014

2014-06-05T12:57:00Z

← Older revision		Revision as of 14:57, 5 June 2014
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	A disruption is a violent event that terminates a magnetically confined plasma, usually the consequence of a rapidly growing instability, often of the MHD type.		A disruption is a violent event that terminates a magnetically confined plasma, usually the consequence of a rapidly growing instability, often of the MHD type.
	<ref>~~[http://dx.doi.org/10.1088/0029-5515/51/5/053018~~ P.C. de Vries et al, ''Survey of disruption causes at JET'', Nucl. Fusion '''51''' (2011) 053018]</ref>		<ref>P.C. de Vries et al, ''Survey of disruption causes at JET'', [[doi:10.1088/0029-5515/51/5/053018\|Nucl. Fusion '''51''' (2011) 053018]]</ref>
	In a disruption, the temperature drops drastically and heat and particles are released from confinement on a short timescale and dumped on the vessel wall, causing damage in proportion to the stored energy. The loss of confinement is associated with the production of runaway electrons, which may also produce damage.		In a disruption, the temperature drops drastically and heat and particles are released from confinement on a short timescale and dumped on the vessel wall, causing damage in proportion to the stored energy. The loss of confinement is associated with the production of runaway electrons, which may also produce damage.
	<ref>~~[http://dx.doi.org/10.1016/S0022-3115(00)00151-3~~ A. Cardella et al, ''Effects of plasma disruption events on ITER first wall materials'', Journal of Nuclear Materials '''283-287''', Part 2 (2000) 1105-1110]</ref>		<ref>A. Cardella et al, ''Effects of plasma disruption events on ITER first wall materials'', [[doi:10.1016/S0022-3115(00)00151-3\|Journal of Nuclear Materials '''283-287''', Part 2 (2000) 1105-1110]]</ref>

	The magnetic effects of a disruption (associated with the sudden loss of the net plasma current) generate large magnetic forces on the metallic structures surrounding the plasma (the vessel, the coils, and the supporting structure), also known as Vertical Displacement Events, which may induce mechanical damage.		The magnetic effects of a disruption (associated with the sudden loss of the net plasma current) generate large magnetic forces on the metallic structures surrounding the plasma (the vessel, the coils, and the supporting structure), also known as Vertical Displacement Events, which may induce mechanical damage.

			== Influence of the magnetic configuration ==

			Due to the fact that in [[Stellarator\|stellarators]], confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future [[Stellarator reactor\|stellarator reactor]].
			<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>

			== Avoidance and mitigation ==

	Disruption avoidance or mitigation is an important topic for [[ITER]].		Disruption avoidance or mitigation is an important topic for [[ITER]].
	<ref>~~[http://dx.doi.org/10.1088/0029-5515/39/12/303~~ ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', Nucl. Fusion '''39 ''' (1999) 2251-2389]</ref>		<ref>ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', [[doi:10.1088/0029-5515/39/12/303\|Nucl. Fusion '''39 ''' (1999) 2251-2389]]</ref>

	~~Due to the fact that in [[Stellarator\|stellarators]]~~, ~~confinement does not depend on the plasma current~~, ~~disruptions are less severe or inexistent in such machines~~, ~~which is a significant advantage~~ for ~~the design of a future~~ [[~~Stellarator reactor~~\|~~stellarator reactor~~]].		Disposing of a good capacity for predicting disruptions is essential when implementing mitigation measures.
	<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. A. Rattá, J. Vega, A. Murari, M. Johnson, and JET-EFDA Contributors, ''Feature extraction for improved disruption prediction analysis at JET'',[[doi:10.1063/1.2965020\|Rev. Sci. Instrum. '''79''' (2008) 10F328]]</ref>
			<ref>G.A. Rattá, J. Vega, A. Murari, G. Vagliasindi, M.F. Johnson, P.C. de Vries and JET EFDA Contributors, ''An advanced disruption predictor for JET tested in a simulated real-time environment'', [[doi:10.1088/0029-5515/50/2/025005\|Nucl. Fusion '''50''' (2010) 025005]]</ref>
			<ref>G.A. Rattá, J. Vega, A. Murari, JET-EFDA Contributors, ''Improved feature selection based on genetic algorithms for real time disruption prediction on JET [[doi:10.1016/j.fusengdes.2012.07.002\|Fusion Engineering and Design '''87''' (2012) 1670–1678]]</ref>

	== References ==		== References ==
	<references />		<references />

Admin at 13:16, 21 July 2011

2011-07-21T13:16:37Z

← Older revision		Revision as of 15:16, 21 July 2011
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	A disruption is a violent event that terminates a magnetically confined plasma, usually the consequence of a rapidly growing instability, often of the MHD type. In a disruption, the temperature drops drastically and heat and particles are released from confinement on a short timescale and dumped on the vessel wall, causing damage in proportion to the stored energy. The loss of confinement is associated with the production of runaway electrons, which may also produce damage.		A disruption is a violent event that terminates a magnetically confined plasma, usually the consequence of a rapidly growing instability, often of the MHD type.
			<ref>[http://dx.doi.org/10.1088/0029-5515/51/5/053018 P.C. de Vries et al, ''Survey of disruption causes at JET'', Nucl. Fusion '''51''' (2011) 053018]</ref>
			In a disruption, the temperature drops drastically and heat and particles are released from confinement on a short timescale and dumped on the vessel wall, causing damage in proportion to the stored energy. The loss of confinement is associated with the production of runaway electrons, which may also produce damage.
	<ref>[http://dx.doi.org/10.1016/S0022-3115(00)00151-3 A. Cardella et al, ''Effects of plasma disruption events on ITER first wall materials'', Journal of Nuclear Materials '''283-287''', Part 2 (2000) 1105-1110]</ref>		<ref>[http://dx.doi.org/10.1016/S0022-3115(00)00151-3 A. Cardella et al, ''Effects of plasma disruption events on ITER first wall materials'', Journal of Nuclear Materials '''283-287''', Part 2 (2000) 1105-1110]</ref>

Admin: Reverted edits by 174.129.205.123 (Talk) to last revision by Admin

2011-05-19T05:24:48Z

Reverted edits by 174.129.205.123 (Talk) to last revision by Admin

← Older revision		Revision as of 07:24, 19 May 2011
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	~~At last! Someone who understands! Thanks~~ for ~~psoitng!~~		A disruption is a violent event that terminates a magnetically confined plasma, usually the consequence of a rapidly growing instability, often of the MHD type. In a disruption, the temperature drops drastically and heat and particles are released from confinement on a short timescale and dumped on the vessel wall, causing damage in proportion to the stored energy. The loss of confinement is associated with the production of runaway electrons, which may also produce damage.
			<ref>[http://dx.doi.org/10.1016/S0022-3115(00)00151-3 A. Cardella et al, ''Effects of plasma disruption events on ITER first wall materials'', Journal of Nuclear Materials '''283-287''', Part 2 (2000) 1105-1110]</ref>

			The magnetic effects of a disruption (associated with the sudden loss of the net plasma current) generate large magnetic forces on the metallic structures surrounding the plasma (the vessel, the coils, and the supporting structure), also known as Vertical Displacement Events, which may induce mechanical damage.

			Disruption avoidance or mitigation is an important topic for [[ITER]].
			<ref>[http://dx.doi.org/10.1088/0029-5515/39/12/303 ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', Nucl. Fusion '''39 ''' (1999) 2251-2389]</ref>

			Due to the fact that in [[Stellarator\|stellarators]], confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future [[Stellarator reactor\|stellarator reactor]].
			<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>

			== References ==
			<references />

174.129.205.123: Undo revision 3039 by Admin (Talk)

2011-05-18T22:51:23Z

Undo revision 3039 by Admin (Talk)

← Older revision		Revision as of 00:51, 19 May 2011
Line 1:		Line 1:
	A disruption is a violent event that terminates a magnetically confined plasma, usually the consequence of a rapidly growing instability, often of the MHD type. In a disruption, the temperature drops drastically and heat and particles are released from confinement on a short timescale and dumped on the vessel wall, causing damage in proportion to the stored energy. The loss of confinement is associated with the production of runaway electrons, which may also produce damage.		At last! Someone who understands! Thanks for psoitng!
	<ref>[http://dx.doi.org/10.1016/S0022-3115(00)00151-3 A. Cardella et al, ''Effects of plasma disruption events on ITER first wall materials'', Journal of Nuclear Materials '''283-287''', Part 2 (2000) 1105-1110]</ref>

	The magnetic effects of a disruption (associated with the sudden loss of the net plasma current) generate large magnetic forces on the metallic structures surrounding the plasma (the vessel, the coils, and the supporting structure), also known as Vertical Displacement Events, which may induce mechanical damage.

	~~Disruption avoidance or mitigation is an important topic~~ for ~~[[ITER]].~~
	<ref>[http://dx.doi.org/10.1088/0029-5515/39/12/303 ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', Nucl. Fusion '''39 ''' (1999) 2251-2389]</ref>

	Due to the fact that in [[Stellarator\|stellarators]], confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future [[Stellarator reactor\|stellarator reactor]].
	~~<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>~~

	~~== References ==~~
	~~<references />~~

Admin at 19:31, 3 May 2011

2011-05-03T19:31:57Z

← Older revision		Revision as of 21:31, 3 May 2011
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	<ref>[http://dx.doi.org/10.1016/S0022-3115(00)00151-3 A. Cardella et al, ''Effects of plasma disruption events on ITER first wall materials'', Journal of Nuclear Materials '''283-287''', Part 2 (2000) 1105-1110]</ref>		<ref>[http://dx.doi.org/10.1016/S0022-3115(00)00151-3 A. Cardella et al, ''Effects of plasma disruption events on ITER first wall materials'', Journal of Nuclear Materials '''283-287''', Part 2 (2000) 1105-1110]</ref>

	The magnetic effects of a disruption (associated with the sudden loss of the net plasma current) ~~generates~~ large magnetic forces on the metallic structures surrounding the plasma (the vessel, the coils, and the supporting structure), also known as Vertical Displacement Events, which may induce mechanical damage.		The magnetic effects of a disruption (associated with the sudden loss of the net plasma current) generate large magnetic forces on the metallic structures surrounding the plasma (the vessel, the coils, and the supporting structure), also known as Vertical Displacement Events, which may induce mechanical damage.

	Disruption avoidance or mitigation is an important topic for [[ITER]].		Disruption avoidance or mitigation is an important topic for [[ITER]].
	<ref>[http://dx.doi.org/10.1088/0029-5515/39/12/303 ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', Nucl. Fusion '''39 ''' (1999) 2251-2389]</ref>		<ref>[http://dx.doi.org/10.1088/0029-5515/39/12/303 ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', Nucl. Fusion '''39 ''' (1999) 2251-2389]</ref>

	Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future [[Stellarator reactor\|stellarator reactor]].		Due to the fact that in [[Stellarator\|stellarators]], confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future [[Stellarator reactor\|stellarator reactor]].
	<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>

	== References ==		== References ==
	<references />		<references />

Admin at 07:44, 9 September 2009

2009-09-09T07:44:27Z

← Older revision		Revision as of 09:44, 9 September 2009
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	<ref>[http://dx.doi.org/10.1088/0029-5515/39/12/303 ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', Nucl. Fusion '''39 ''' (1999) 2251-2389]</ref>		<ref>[http://dx.doi.org/10.1088/0029-5515/39/12/303 ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', Nucl. Fusion '''39 ''' (1999) 2251-2389]</ref>

	Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future reactor.		Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future [[Stellarator reactor\|stellarator reactor]].
	<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://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>

	== References ==		== References ==
	<references />		<references />

Admin at 07:43, 9 September 2009

2009-09-09T07:43:10Z

← Older revision		Revision as of 09:43, 9 September 2009
Line 8:		Line 8:

	Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future reactor.		Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future reactor.
			<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://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>

	== References ==		== References ==
	<references />		<references />

Admin at 07:40, 9 September 2009

2009-09-09T07:40:07Z

← Older revision		Revision as of 09:40, 9 September 2009
Line 8:		Line 8:

	Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future reactor.		Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future reactor.
			<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>

	== References ==		== References ==
	<references />		<references />

Admin at 12:02, 7 September 2009

2009-09-07T12:02:16Z

← Older revision		Revision as of 14:02, 7 September 2009
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	Disruption avoidance or mitigation is an important topic for [[ITER]].		Disruption avoidance or mitigation is an important topic for [[ITER]].
			<ref>[http://dx.doi.org/10.1088/0029-5515/39/12/303 ITER Physics Expert Group on Disruptions, Plasma Control, and MHD, ''ITER Physics Basis Chapter 3: MHD stability, operational limits and disruptions'', Nucl. Fusion '''39 ''' (1999) 2251-2389]</ref>

	Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future reactor.		Due to the fact that in stellarators, confinement does not depend on the plasma current, disruptions are less severe or inexistent in such machines, which is a significant advantage for the design of a future reactor.