Let us make sure when we use the words poloidal and toroidal that we define the usage.
When someones says 'poloidal winding' it refers to the 'winding', not the field.
Agreed. By the same token, if someone says 'TFC' it would be in reference to the 'poloidal winding'.
Both patent drawing examples are correct. One refers to the windings the other refers to the field created.
Respectfully, this is not so. Both diagrams are labeled and/or referred to in the patent text as "coils" or "windings", so it is impossible to conclude that they are both correct. In the technical sense, clearly one is not correct, and that would be the Delvecchio patent I posted. Had he included the word "field", he would be correct. Perhaps he got lazy and dropped "field" from the term, or perhaps this has become the convention. I would suspect the latter, as everything I've come across uses this terminology. Interestingly, the Prueitt patent references the Delvecchio patents.
The Tokamak users also refer to windings as to what they are and not what they create.
Again, this is simply not so. Have a look again at the Tokamak diagram I posted (and several others included below). I've done additional research and in reference to the
iter and
JET Tokamaks, and others, they
ALWAYS refer to the
fields when referencing the coils. I'd be interested to see your research and any reference which proves the contrary. If they do exist, they would certainly occupy only a tiny minority.
From the glossary of
iter terms here:
http://www.iter.org/glossary"
iter" being the world's largest Tokamak under construction:
Poloidal Direction: Movement in the vertical plane intersecting the plasma torus along projections in that plane of any of the tokamak's nested toroidal flux surfaces.
Poloidal Field: The magnetic field generated by an electric current flowing in a ring. In toroidal devices, the magnetic field that encircles the plasma axis. (i.e. loops around the torus the short way.)
Poloidal Field Coils: Components of a tokamak that assist in stabilizing the plasma.
In ITER, the Poloidal Field coil system consists of six horizontal coils placed outside the Toroidal Magnet structure.Toroidal Direction: In a doughnut-shaped torus, the direction parallel to the large circumference.
Toroidal Field: The magnetic field generated by an electrical currrent flowing around a torus.
Toroidal Field Coils: Components of a tokamak that assist in stabilizing the plasma, by creating a 'magnetic bottle' for confinement.
In ITER, the Toroidal Field coil system consists of 18 D-shaped vertical coils placed around the Vacuum Vessel.Another
good document from
iter.
From the
JET website,
a good document "
The Science of JET" which clearly indicates the coil terminology used throughout in Tokamak research. There are many good documents discussing the project.
JET is the "Joint European Torus",
Europe's largest fusion device. I think we would be remiss in saying that these many Tokamak physicists got the coil terminology wrong.
There are hundreds of references out there on Tokamak technology and "plasma confinement" using the orthogonal coil method, and in my findings, they all agree on the coil reference terminology noted in the glossary above and all the illustrations that can be found on the Tokamak. Included below are a few more of those illustrations:
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Topic: Toroidal and Polodial - Which is Which? (Read 19768 times)
