VMEC - Revision history

Admin: /* See also */

2019-08-07T13:47:51Z

Admin: /* See also */

2018-10-25T08:33:09Z

Admin at 07:48, 22 January 2015

2015-01-22T07:48:29Z

← Older revision		Revision as of 09:48, 22 January 2015
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	The code assumes nested flux surfaces.		The code assumes nested flux surfaces.
	<ref>~~[[doi:10.1063/1.864116\|~~S.P. Hirschman et al, ''Steepest-descent moment method for three-dimensional magnetohydrodynamic equilibria'', Phys. Fluids '''26''' (1983) 3553]]</ref>		<ref>S.P. Hirschman et al, ''Steepest-descent moment method for three-dimensional magnetohydrodynamic equilibria'', [[doi:10.1063/1.864116\|Phys. Fluids '''26''' (1983) 3553]]</ref>
	<ref>~~[[doi:10.1016/0010-4655(86)90058-5\|~~S.P. Hirschman et al, ''Three-dimensional free boundary calculations using a spectral Green's function method'', Computer Physics Communications '''43''', 1 (1986) 143-155]]</ref>		<ref>S.P. Hirschman et al, ''Three-dimensional free boundary calculations using a spectral Green's function method'', [[doi:10.1016/0010-4655(86)90058-5\|Computer Physics Communications '''43''', 1 (1986) 143-155]]</ref>

	== Uses of the code ==		== Uses of the code ==
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	Due to its speed in computing the MHD equilibrium problem in 3-D it has become the "de facto" standard code for calculating 3-D equilibria. This means that practically all the laboratories		Due to its speed in computing the MHD equilibrium problem in 3-D it has become the "de facto" standard code for calculating 3-D equilibria. This means that practically all the laboratories
	with stellerator devices routinely use it. It has also been used to model tokamak equilibria and lately (2010) it has been applied to reverse field pinches, in particular helical equilibria (non-axisymmetric) in the RFX-Mod.		with stellerator devices routinely use it. It has also been used to model tokamak equilibria and lately (2010) it has been applied to reverse field pinches, in particular helical equilibria (non-axisymmetric) in the RFX-Mod.
	<ref>~~[[doi:10.1002/ctpp.200900010\|~~D. Terranova et al., ''Self-Organized Helical Equilibria in the RFX-Mod Reversed Field Pinch'', Contributions to Plasma Physics '''50''' (2010) 775–779]]</ref>		<ref>D. Terranova et al., ''Self-Organized Helical Equilibria in the RFX-Mod Reversed Field Pinch'', [[doi:10.1002/ctpp.200900010\|Contributions to Plasma Physics '''50''' (2010) 775–779]]</ref>

	The code is being used at fusion laboratories all over the world:		The code is being used at fusion laboratories all over the world:
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	== Enhancements / extensions of the code ==		== Enhancements / extensions of the code ==

	* DIAGNO, <ref>~~[[doi:10.1088/0029-5515/30/8/002\|~~H.J. Gardner, ''Modelling the behaviour of the magnetic field diagnostic coils on the W VII-AS stellarator using a three-dimensional equilibrium code'', Nucl. Fusion '''30''' (1990) 1417]]</ref> to calculate the response of magnetic diagnostics		* DIAGNO, <ref>H.J. Gardner, ''Modelling the behaviour of the magnetic field diagnostic coils on the W VII-AS stellarator using a three-dimensional equilibrium code'', [[doi:10.1088/0029-5515/30/8/002\|Nucl. Fusion '''30''' (1990) 1417]]</ref> to calculate the response of magnetic diagnostics
	* MFBE <ref>~~[[doi:10.1088/0029-5515/37/1/I03\|~~E. Strumberger, ''Finite-β magnetic field line tracing for Helias configurations'', Nucl. Fusion '''37''' (1997) 19]]</ref>		* MFBE <ref>E. Strumberger, ''Finite-β magnetic field line tracing for Helias configurations'', [[doi:10.1088/0029-5515/37/1/I03\|Nucl. Fusion '''37''' (1997) 19]]</ref>
	* STELLOPT <ref>~~[[doi:10.1088/0029-5515/41/6/305\|~~D.A. Spong et al., ''Physics issues of compact drift optimized stellarators'', Nucl. Fusion '''41''' (2001) 711]]</ref>		* STELLOPT <ref>D.A. Spong et al., ''Physics issues of compact drift optimized stellarators'', [[doi:10.1088/0029-5515/41/6/305\|Nucl. Fusion '''41''' (2001) 711]]</ref>

	== See also ==		== See also ==

Admin at 10:28, 15 August 2012

2012-08-15T10:28:39Z

← Older revision		Revision as of 12:28, 15 August 2012
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	== References ==		== References ==
	<references />		<references />

			[[Category:Software]]

Admin at 07:33, 14 August 2011

2011-08-14T07:33:37Z

Admin: /* Enhancements / extensions of the code */

2011-08-13T19:33:45Z

Enhancements / extensions of the code

← Older revision		Revision as of 21:33, 13 August 2011
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	* MFBE <ref>[http://dx.doi.org/10.1088/0029-5515/37/1/I03 E. Strumberger, ''Finite-β magnetic field line tracing for Helias configurations'', Nucl. Fusion '''37''' (1997) 19]</ref>		* MFBE <ref>[http://dx.doi.org/10.1088/0029-5515/37/1/I03 E. Strumberger, ''Finite-β magnetic field line tracing for Helias configurations'', Nucl. Fusion '''37''' (1997) 19]</ref>
	* STELLOPT <ref>[http://dx.doi.org/10.1088/0029-5515/41/6/305 D.A. Spong et al., ''Physics issues of compact drift optimized stellarators'', Nucl. Fusion '''41''' (2001) 711]</ref>		* STELLOPT <ref>[http://dx.doi.org/10.1088/0029-5515/41/6/305 D.A. Spong et al., ''Physics issues of compact drift optimized stellarators'', Nucl. Fusion '''41''' (2001) 711]</ref>

			== See also ==

			* [http://vmecwiki.pppl.wikispaces.net/ VMECwiki]

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

10.10.119.10: /* Uses of the code */

2010-11-03T14:47:42Z

Uses of the code

← Older revision		Revision as of 16:47, 3 November 2010
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	* NIFS, Toki, Japan		* NIFS, Toki, Japan
	* RFX, Padova. Italy		* RFX, Padova. Italy
	* UW, Madison, WI, USA		* [http://www.hsx.wisc.edu/ HSX], Madison, WI, USA
	* [[Laboratorio Nacional de Fusión\|LNF]], Madrid, Spain		* [[Laboratorio Nacional de Fusión\|LNF]], Madrid, Spain

10.10.119.10: /* Uses of the code */

2010-11-03T14:20:48Z

Uses of the code

← Older revision		Revision as of 16:20, 3 November 2010
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	* IPP, at Garching and Greifswald, Germany		* IPP, at Garching and Greifswald, Germany
	* CRPP, Lausanne, Switzerland		* CRPP, Lausanne, Switzerland
	* NIFS, Japan		* NIFS, Toki, Japan
	* RFX, Padova. Italy		* RFX, Padova. Italy
	* ~~HSX~~, Madison, USA		* UW, Madison, WI, USA
	* [[Laboratorio Nacional de Fusión\|LNF]], Spain		* [[Laboratorio Nacional de Fusión\|LNF]], Madrid, Spain

	== Enhancements / extensions of the code ==		== Enhancements / extensions of the code ==

10.10.119.10: /* Uses of the code */

2010-11-03T14:17:07Z

Uses of the code

← Older revision		Revision as of 16:17, 3 November 2010
Line 19:		Line 19:

	Due to its speed in computing the MHD equilibrium problem in 3-D it has become the "de facto" standard code for calculating 3-D equilibria. This means that practically all the laboratories		Due to its speed in computing the MHD equilibrium problem in 3-D it has become the "de facto" standard code for calculating 3-D equilibria. This means that practically all the laboratories
	with stellerator devices ~~uses~~ it. It has also been used to model tokamak equilibria and lately (2010) it has been applied to reverse field pinches, in particular helical equilibria (non-axisymmetric) in the RFX-Mod.		with stellerator devices routinely use it. It has also been used to model tokamak equilibria and lately (2010) it has been applied to reverse field pinches, in particular helical equilibria (non-axisymmetric) in the RFX-Mod.
	<ref>[http://onlinelibrary.wiley.com/doi/10.1002/ctpp.200900010/abstract;jsessionid=4984B4F8ECA726F21E87571E4C98F904.d03t01 D. Terranova et al., ''Self-Organized Helical Equilibria in the RFX-Mod Reversed Field Pinch'', Contributions to Plasma Physics '''50''' (2010) 775–779]</ref>		<ref>[http://onlinelibrary.wiley.com/doi/10.1002/ctpp.200900010/abstract;jsessionid=4984B4F8ECA726F21E87571E4C98F904.d03t01 D. Terranova et al., ''Self-Organized Helical Equilibria in the RFX-Mod Reversed Field Pinch'', Contributions to Plasma Physics '''50''' (2010) 775–779]</ref>

10.10.119.10 at 14:16, 3 November 2010

2010-11-03T14:16:26Z

← Older revision		Revision as of 16:16, 3 November 2010
Line 20:		Line 20:
	Due to its speed in computing the MHD equilibrium problem in 3-D it has become the "de facto" standard code for calculating 3-D equilibria. This means that practically all the laboratories		Due to its speed in computing the MHD equilibrium problem in 3-D it has become the "de facto" standard code for calculating 3-D equilibria. This means that practically all the laboratories
	with stellerator devices uses it. It has also been used to model tokamak equilibria and lately (2010) it has been applied to reverse field pinches, in particular helical equilibria (non-axisymmetric) in the RFX-Mod.		with stellerator devices uses it. It has also been used to model tokamak equilibria and lately (2010) it has been applied to reverse field pinches, in particular helical equilibria (non-axisymmetric) in the RFX-Mod.
	<ref>[http://onlinelibrary.wiley.com/doi/10.1002/ctpp.200900010/abstract;jsessionid=4984B4F8ECA726F21E87571E4C98F904.d03t01 D. Terranova et al., ''Self-Organized Helical Equilibria in the RFX-Mod Reversed Field Pinch'', Contributions to Plasma Physics "50" (2010) 775–779]</ref>		<ref>[http://onlinelibrary.wiley.com/doi/10.1002/ctpp.200900010/abstract;jsessionid=4984B4F8ECA726F21E87571E4C98F904.d03t01 D. Terranova et al., ''Self-Organized Helical Equilibria in the RFX-Mod Reversed Field Pinch'', Contributions to Plasma Physics '''50''' (2010) 775–779]</ref>

	The code is being used at fusion laboratories all over the world:		The code is being used at fusion laboratories all over the world:

← Older revision		Revision as of 15:47, 7 August 2019
Line 41:		Line 41:
	== See also ==		== See also ==

	* [https://~~bitbucket~~.~~org/lazerson_princeton/stellopt~~/~~wiki~~/~~Home~~ VMECwiki]		* [https://princetonuniversity.github.io/STELLOPT/ VMECwiki]

	== References ==		== References ==

← Older revision		Revision as of 10:33, 25 October 2018
Line 41:		Line 41:
	== See also ==		== See also ==

	* [~~http~~://~~vmecwiki~~.~~pppl.wikispaces.net~~/ VMECwiki]		* [https://bitbucket.org/lazerson_princeton/stellopt/wiki/Home VMECwiki]

	== References ==		== References ==

← Older revision		Revision as of 09:33, 14 August 2011
Line 13:		Line 13:

	The code assumes nested flux surfaces.		The code assumes nested flux surfaces.
	<ref>[~~http~~:~~//dx.doi.org/~~10.1063/1.864116 S.P. Hirschman et al, ''Steepest-descent moment method for three-dimensional magnetohydrodynamic equilibria'', Phys. Fluids '''26''' (1983) 3553]</ref>		<ref>[[doi:10.1063/1.864116\|S.P. Hirschman et al, ''Steepest-descent moment method for three-dimensional magnetohydrodynamic equilibria'', Phys. Fluids '''26''' (1983) 3553]]</ref>
	<ref>[~~http~~:~~//dx.doi.org/~~10.1016/0010-4655(86)90058-5 S.P. Hirschman et al, ''Three-dimensional free boundary calculations using a spectral Green's function method'', Computer Physics Communications '''43''', 1 (1986) 143-155]</ref>		<ref>[[doi:10.1016/0010-4655(86)90058-5\|S.P. Hirschman et al, ''Three-dimensional free boundary calculations using a spectral Green's function method'', Computer Physics Communications '''43''', 1 (1986) 143-155]]</ref>

	== Uses of the code ==		== Uses of the code ==
Line 20:		Line 20:
	Due to its speed in computing the MHD equilibrium problem in 3-D it has become the "de facto" standard code for calculating 3-D equilibria. This means that practically all the laboratories		Due to its speed in computing the MHD equilibrium problem in 3-D it has become the "de facto" standard code for calculating 3-D equilibria. This means that practically all the laboratories
	with stellerator devices routinely use it. It has also been used to model tokamak equilibria and lately (2010) it has been applied to reverse field pinches, in particular helical equilibria (non-axisymmetric) in the RFX-Mod.		with stellerator devices routinely use it. It has also been used to model tokamak equilibria and lately (2010) it has been applied to reverse field pinches, in particular helical equilibria (non-axisymmetric) in the RFX-Mod.
	<ref>[~~http~~:~~//onlinelibrary.wiley.com/doi/~~10.1002/ctpp.200900010~~/abstract;jsessionid=4984B4F8ECA726F21E87571E4C98F904.d03t01~~ D. Terranova et al., ''Self-Organized Helical Equilibria in the RFX-Mod Reversed Field Pinch'', Contributions to Plasma Physics '''50''' (2010) 775–779]</ref>		<ref>[[doi:10.1002/ctpp.200900010\|D. Terranova et al., ''Self-Organized Helical Equilibria in the RFX-Mod Reversed Field Pinch'', Contributions to Plasma Physics '''50''' (2010) 775–779]]</ref>

	The code is being used at fusion laboratories all over the world:		The code is being used at fusion laboratories all over the world:
Line 35:		Line 35:
	== Enhancements / extensions of the code ==		== Enhancements / extensions of the code ==

	* DIAGNO, <ref>H.J. Gardner, Nucl. Fusion '''30''' (1990) 1417</ref> to calculate the response of magnetic diagnostics		* DIAGNO, <ref>[[doi:10.1088/0029-5515/30/8/002\|H.J. Gardner, ''Modelling the behaviour of the magnetic field diagnostic coils on the W VII-AS stellarator using a three-dimensional equilibrium code'', Nucl. Fusion '''30''' (1990) 1417]]</ref> to calculate the response of magnetic diagnostics
	* MFBE <ref>[~~http~~:~~//dx.doi.org/~~10.1088/0029-5515/37/1/I03 E. Strumberger, ''Finite-β magnetic field line tracing for Helias configurations'', Nucl. Fusion '''37''' (1997) 19]</ref>		* MFBE <ref>[[doi:10.1088/0029-5515/37/1/I03\|E. Strumberger, ''Finite-β magnetic field line tracing for Helias configurations'', Nucl. Fusion '''37''' (1997) 19]]</ref>
	* STELLOPT <ref>[~~http~~:~~//dx.doi.org/~~10.1088/0029-5515/41/6/305 D.A. Spong et al., ''Physics issues of compact drift optimized stellarators'', Nucl. Fusion '''41''' (2001) 711]</ref>		* STELLOPT <ref>[[doi:10.1088/0029-5515/41/6/305\|D.A. Spong et al., ''Physics issues of compact drift optimized stellarators'', Nucl. Fusion '''41''' (2001) 711]]</ref>

	== See also ==		== See also ==