VMEC: Difference between revisions

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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 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:

Revision as of 15:16, 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. [3]

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, [4] to calculate the response of magnetic diagnostics
  • MFBE [5]
  • STELLOPT [6]

References