Stellarator-spheromak

Moroz, Paul

doi:10.1016/s0375-9601(97)00668-3

Cited by 4 publications

(7 citation statements)

References 17 publications

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“…They could be more appropriately referred to as a hybrid between a compact tokamak (CT) and a sphellamak. A similar system, the stellarator-spheromak, was proposed and its 3D equilibrium properties investigated [8]. The configurations identified, however, can be more closely identified with classical stellarators because the magnetic field distribution displays a more noticeable 3D structure than the systems examined in this paper.…”

Section: Introductionmentioning

confidence: 78%

Effect of helical coils on the magnetic field and the stability of a compact toroidal plasma

Cooper

Todd

Allfrey

et al. 2000

Plasma Phys. Control. Fusion

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The helical distortion of a compact tokamak plasma with currents in modular Furth-Hartman type coils is investigated with respect to the impact on the magnetic field structure and to the ideal magnetohydrodynamic stability. A sequence of configurations, in which the current in the helical coils is increased up to the level of that of the main toroidal coils, is generated. The magnetic field structure acquires a ripple along the field lines when the currents in both sets of coils becomes comparable. The magnitude of this ripple depends on the modulation of the Furth-Hartman coils on their winding surface. The local ideal ballooning stability properties deteriorate with the increasing helical deformation of the plasma shape because the normal magnetic field line curvature becomes larger in regions where the helical contribution enhances the toroidicity component while the local magnetic shear vanishes. The global external kink stability properties, in contrast, improve because the normal curvature on average does not change while the local magnetic shear acquires a noticeable helical modulation.

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Section: Introductionmentioning

confidence: 78%

Effect of helical coils on the magnetic field and the stability of a compact toroidal plasma

Cooper

Todd

Allfrey

et al. 2000

Plasma Phys. Control. Fusion

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“…The only helical elements of the DHS configuration considered are the two helical windings replacing the centre post of a standard spherical tokamak coil system. Actually, the DHS features one of the most compact and most spherical plasmas among all the SS configurations [2][3][4][5][6][7][8][9][10][11] and satisfies all the SS requirements. Thus, it can be considered a new member of the SS family as well.…”

Section: Discussionmentioning

confidence: 99%

“…More recently, a few other publications [7][8][9][10][11][12][13][14][15][16] have appeared on this topic and some other US institutions have become involved in this kind of low aspect ratio stellarator research. Researchers at ORNL focus on J * transport optimization.…”

Section: Introductionmentioning

confidence: 99%

Novel stellarator configuration with double helix centre post

Moroz¹

1998

Nucl. Fusion

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A novel stellarator configuration, the double helix stellarator (DHS), is introduced. It is produced by a double helix centre post and has many unique characteristics. Among them are extreme low plasma aspect ratios, A M 1, significant rotational transform and extreme-high-P MHD equilibria. Other advantages include a high enclosed volume, absence of noticeable magnetic islands and improved particle transport caused by the absence of a magnetic field ripple on the outboard part of the torus. Compactness, simplicity and modularity of the coil system add to the advantages of the DHS configuration for fusion applications

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“…In some of them the coils were planar [18,19,22], including noncircular shapes [18,22]. In others they were non-planar [20,21,[23][24][25][26], e.g.helical on the inboard [24,25] or outboard side [21,23], as also proposed [27][28][29] and experimentally realized [30] elsewhere.…”

Section: Brief Review Of Tilted-coil Devicesmentioning

confidence: 94%

“…Starting in the mid-1990s, Moroz numerically investigated several non-interlinked configurations [18][19][20][21][22][23][24][25]. In some of them the coils were planar [18,19,22], including noncircular shapes [18,22].…”

Section: Brief Review Of Tilted-coil Devicesmentioning

confidence: 99%

Large vacuum flux surfaces generated by tilted planar coils

Austin

Hammond

et al. 2019

Plasma Phys. Control. Fusion

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Helical equilibria can be generated by arrangements of planar coils similar to tokamaks, but without a central solenoid and with the toroidal field (TF) coils tilted with respect to the vertical. This is known from earlier numerical works, e.g. P.E. Moroz, Phys. Plasmas 2, 4269 (1995). However, such concept tends to need large coils (of low aspect ratio) but form small plasmas (of large aspect ratio). Here it is numerically shown that larger, more attractive vacuum flux surfaces -relative to the size of the device-can be generated by carefully optimizing the inclination of the TF coils and currents in the various coil-sets. Vacuum configurations of aspect ratios as low as 4 are found for 6 tilted TF circular coils. Higher numbers of TF coils have advantages (smaller effective ripple) and disadvantages (lower rotational transform, smaller plasma). Finally, the aspect-ratio A of the vacuum flux surfaces is quantified as a function of the ratio A c of the coil-radius to the radial location of the coil-center. It is found that, in order to minimize A, it is beneficial to interlink or marginally interlink the TF coils (A c 1).

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Stellarator-spheromak

Cited by 4 publications

References 17 publications

Effect of helical coils on the magnetic field and the stability of a compact toroidal plasma

Effect of helical coils on the magnetic field and the stability of a compact toroidal plasma

Novel stellarator configuration with double helix centre post

Large vacuum flux surfaces generated by tilted planar coils

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