VMEC: Difference between revisions

2 bytes removed ,  22 January 2015
no edit summary
No edit summary
No edit summary
Line 13: Line 13:


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 ==
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>[[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:
Line 35: Line 35:
== 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-&beta; magnetic field line tracing for Helias configurations'', Nucl. Fusion '''37''' (1997) 19]]</ref>
* MFBE <ref>E. Strumberger, ''Finite-&beta; 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 ==