Ellipticity: Difference between revisions

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m (Mention typical max kappa value)
(Add a figure with simple illustrations of Shafranov shift, elongation, triangularity, and squareness.)
 
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[[File:Geometry.png|400px|thumb|right|Sketch of tokamak geometry]]  
[[File:Geometry.png|400px|thumb|right|Sketch of tokamak geometry]]
[[File:Cross_section_1shift_2elong_3triang_4square.png|400px|thumb|right|Illustration of the m=1,2,3, and 4 perturbations to a tokamak plasma cross section. Ellipticity/elongation is the m=2 perturbation (second from the left).]]
The ellipticity (also referred to as elongation<ref name="Luce2013">T.C. Luce, [[doi:10.1088/0741-3335/55/9/095009|Plasma Phys. Control. Fusion '''55''' (2013) 095009 ]]</ref>) refers to the shape of the poloidal cross section of the Last Closed [[Flux surface]] or [[separatrix]] of a [[tokamak]].
The ellipticity (also referred to as elongation<ref name="Luce2013">T.C. Luce, [[doi:10.1088/0741-3335/55/9/095009|Plasma Phys. Control. Fusion '''55''' (2013) 095009 ]]</ref>) refers to the shape of the poloidal cross section of the Last Closed [[Flux surface]] or [[separatrix]] of a [[tokamak]].



Latest revision as of 22:47, 30 March 2023

Sketch of tokamak geometry
Illustration of the m=1,2,3, and 4 perturbations to a tokamak plasma cross section. Ellipticity/elongation is the m=2 perturbation (second from the left).

The ellipticity (also referred to as elongation[1]) refers to the shape of the poloidal cross section of the Last Closed Flux surface or separatrix of a tokamak.

Assuming[1]:

  • Rmax is the maximum value of R along the LCFS or separatrix.
  • Rmin is the minimum value of R along the LCFS or separatrix.
  • Zmax is the maximum value of Z along the LCFS or separatrix.
  • Zmin is the minimum value of Z along the LCFS or separatrix.
  • a is the minor radius of the plasma, defined as (Rmax - Rmin)/2.

The ellipticity is then defined as follows:

Higher elongation is beneficial for fusion performance, but comes with increased vertical instability growth rate and thus increased risk of vertical displacement event (VDE) type disruptions.[2] Because of vertical stability constraints, is usually limited to a value close to about 1.8.

See also

References

  1. 1.0 1.1 T.C. Luce, Plasma Phys. Control. Fusion 55 (2013) 095009
  2. D.A. Humphreys, et al., Experimental vertical stability studies for ITER performance and design guidance Nucl. Fusion 49 (2009) 115003