VMEC: Difference between revisions

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<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>[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>


== Implementations of the code ==
== Uses of the code ==
 
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
http://onlinelibrary.wiley.com/doi/10.1002/ctpp.200900010/abstract;jsessionid=4984B4F8ECA726F21E87571E4C98F904.d03t01
 
The code is being used at fusion laboratories all over the world:


The code is being used at:
* ORNL, Oak Ridge, TN, USA ([http://www.ornl.gov/sci/fed/Theory/stci/code_library.html code origin])
* ORNL, Oak Ridge, TN, USA ([http://www.ornl.gov/sci/fed/Theory/stci/code_library.html code origin])
* PPPL, Princeton, NJ, USA
* PPPL, Princeton, NJ, USA
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* NIFS, Japan
* NIFS, Japan
* RFX, Padova. Italy
* RFX, Padova. Italy
* HSX, Madison, USA
* [[Laboratorio Nacional de Fusión|LNF]], Spain
* [[Laboratorio Nacional de Fusión|LNF]], Spain



Revision as of 15:10, 3 November 2010

The three-dimensional Variational Moments Equilibrium Code (VMEC) minimizes the energy functional

over the toroidal domain Ωp. The solution is obtained in flux coordinates (s, θ, ζ), related to the cylindrical coordinates (R, φ, Z) by

The code assumes nested flux surfaces. [1] [2]

Uses of the code

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 http://onlinelibrary.wiley.com/doi/10.1002/ctpp.200900010/abstract;jsessionid=4984B4F8ECA726F21E87571E4C98F904.d03t01

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

  • ORNL, Oak Ridge, TN, USA (code origin)
  • PPPL, Princeton, NJ, USA
  • IPP, at Garching and Greifswald, Germany
  • CRPP, Lausanne, Switzerland
  • NIFS, Japan
  • RFX, Padova. Italy
  • HSX, Madison, USA
  • LNF, Spain

Enhancements / extensions of the code

  • DIAGNO, [3] to calculate the response of magnetic diagnostics
  • MFBE [4]
  • STELLOPT [5]

References