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TJ-II:Coil system: Difference between revisions
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[[File:TJ-II_Helical_coil.jpg|400px|thumb|right|The core coil pack consists of three coils: the circular core (CC), the helix 1 (HX1), and the helix 2 (HX2).]] | [[File:TJ-II_Helical_coil.jpg|400px|thumb|right|The core coil pack consists of three coils: the circular core (CC), the helix 1 (HX1), and the helix 2 (HX2).]] | ||
The [[TJ-II]] coil system is listed in the table below. | The [[TJ-II]] coil system is listed in the table below (in [[Toroidal coordinates|cylindrical coordinates]]). | ||
All coils are directly [[TJ-II:Cooling system|cooled]] by water flowing trough longitudinal holes in the conductors. | All coils are circular, except the helical coil. | ||
They are directly [[TJ-II:Cooling system|cooled]] by water flowing trough longitudinal holes in the conductors. | |||
All coils have a reinforced structure to avoid mechanical deformations.<ref>M. Medrano, M. Blaumoser, J. Alonso, G. Barrera, M. Pastor, C. Rubio, F. Pedrazo, and O. Heusmann, ''Strength considerations on the magnetic field coils of the Spanish Stellarator TJ-II'', [[doi:10.1109/FUSION.1993.518529| Fusion Engineering, 15th IEEE/NPSS Symposium (1993)]]</ref> | All coils have a reinforced structure to avoid mechanical deformations.<ref>M. Medrano, M. Blaumoser, J. Alonso, G. Barrera, M. Pastor, C. Rubio, F. Pedrazo, and O. Heusmann, ''Strength considerations on the magnetic field coils of the Spanish Stellarator TJ-II'', [[doi:10.1109/FUSION.1993.518529| Fusion Engineering, 15th IEEE/NPSS Symposium (1993)]]</ref> | ||
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|Circular (CC) || 1 || ''R'' = 1.5 || ''Z'' = 0 || 24 | |Circular (CC) || 1 || ''R'' = 1.5 || ''Z'' = 0 || 24 | ||
|- | |- | ||
|Helical (HX)<ref>J. Alonso and M. Blaumoser, ''Design and feasibility of the TJ-II hard core'', [[doi:10.1109/FUSION.1991.218810|Fusion Engineering, 14th IEEE/NPSS Symposium (1991)]]</ref> || 1 || ''R'' = 1.5 <br> swing = 0.07 || || 24 | |Helical (HX)<ref>J. Alonso and M. Blaumoser, ''Design and feasibility of the TJ-II hard core'', [[doi:10.1109/FUSION.1991.218810|Fusion Engineering, 14th IEEE/NPSS Symposium (1991)]]</ref> || 1 || ''R'' = 1.5 <br> swing = 0.07 || ''Z'' = 0 || 24 | ||
|- | |- | ||
|Toroidal (TF) || 28 || ''r'' = 0.425 || ''R'' = 1.5 + 0.2825 cos(4φ) </br> ''Z'' = -0.2825 sin(4φ) || 8 | |Toroidal (TF) || 28 || ''r'' = 0.425 || ''R'' = 1.5 + 0.2825 cos(4φ) </br> ''Z'' = -0.2825 sin(4φ) || 8 | ||
|- | |- | ||
|Toroidal (TF) || 4 || ''r'' = 0.475 || ''R'' = 1.5 + 0. | |Toroidal (TF) || 4 || ''r'' = 0.475 || ''R'' = 1.5 + 0.3325 cos(4φ) </br> ''Z'' = -0.3325 sin(4φ) </br> φ = 0, 90, 180, 270°|| 9 | ||
|- | |- | ||
|Vertical (VF) || 2 || ''R'' = 2.25 || ''Z'' = ± 0.75 || 16 | |Vertical (VF) || 2 || ''R'' = 2.25 || ''Z'' = ± 0.75 || 16 | ||
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The ohmic coils (OH) can generate a loop voltage of 0.1 V, intended to cancel spurious toroidal currents. | The ohmic coils (OH) can generate a loop voltage of 0.1 V, intended to cancel spurious toroidal currents. | ||
The radial coils (R) produce a trimming radial field of up to 100 G, intended to compensate stray fields. | The radial coils (R) produce a trimming radial field of up to 100 G, intended to compensate stray fields. | ||
Currents in the coil sets can be controlled in Autonomous Mode (or `A Mode') or Controlled Mode (or `C mode')<ref>A. de la Peña, L. Pacios, R. Carrasco, F. Lapayese,''A real-time current driving control system for the TJ-II coils'', [[doi:10.1016/j.fusengdes.2008.12.010|Fusion Engineering and Design '''84''', Issues 2–6 (2009) 676-680]]</ref>. | |||
[[File:TJ-II_Coils.png|800px|thumb|Center|TJ-II Coils. Red: central. Yellow: helical. Blue: toroidal. Green: vertical. Brown and green: radial.]] | [[File:TJ-II_Coils.png|800px|thumb|Center|TJ-II Coils. Red: central. Yellow: helical. Blue: toroidal. Green: vertical. Brown and green: radial.]] | ||