Physics of fusion power Lecture 10: tokamak - seallarator.
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Transcript of Physics of fusion power Lecture 10: tokamak - seallarator.
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Physics of fusion power
Lecture 10: tokamak - seallarator
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Tokamak
Bend the theta pinch into a donut shape
No end losses because the field lines go around and close on themselves
Schematic picture of the tokamak
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Toroidal curvature
The magnetic field follows form
And therefore varies with major radius R as
Top view of the tokamak
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Toroidal curvature
The toroidal magnetic field has a gradient
Which leads to a drift in the vertical direction
Note that the sign of the drift depends on the sign of the charge q
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Toroidal curvature
The drift
Leads to charge separation Build up of an electric field
(calculate through the balance with polarization)
And then to an ExB velocity
Poloidal cut of the tokamak.
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Toroidal curvature has its price
The ExB velocity
Is directed outward and will move the plasma on the wall in a short timescale
This effect is no surprise since
Poloidal cut of the tokamak.
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Remedy : a plasma current
A toroidal current in the plasma will generate a poloidal field
Top and bottom are connected by the magnetic field line
A vertical electric field would have a component along the field and leads to acceleration of the ions / electrons
Drift will be balanced by a return flow along the field Poloidal cut of the tokamak.
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Plasma current
Because of the plasma current the field lines wind around hellically
Resistivity is small but finite
Note that the toroidal electric field that drives the current can not be electro-static
The field lines wind around helically .
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Maybe easier to understand
For every toroidal angle the ions drift up and the electrons drift down
A helical field line will therefore connected the regions of ‘positive and negative’ charge
Electrons are accelerated along the field line, and neutrality can be maintained
Note it does lead to parallel flows (with a toroidal component) Attempt at a 3D view. The toroidal
plasma is drawn as a cylinder
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Electric field induced
An iron core on the axis of symmetry is added
The magnetic flux through the iron core is increase
This generates a toroidal electric field Top view of the tokamak. An iron
core is added through which the magnetic flux is increased
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The toroidal electric field
Plasma is the second winding of a transformer
Flux in the iron core cannot be increased forever. The tokamak is necessarily a pulsed machine
That is not good for energy production
Also thermal stresses are associated with the pulsed character
One can either: live with it / drive current another way / use a different concept
The plasma is the second winding of a transformer.
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Do we really need the plasma current?
It might at first appear obvious that the answer is yes since without current inside the plasma
But a positive as well as negative poloidal field does not necessarily mean that the field line on average does not go around poloidally
On average the field line can go around even if the enclosed current is zero.
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Toroidal symmetry
At some point the poloidal field must be zero
In the case of toroidal symmetry this field line closes upon itself
Regions of positive and negative field are not connected
A field line can not wind around poloidally
Then top and bottom can not be connected
With toroidal symmetry one field line can not wind around poloidally
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Same thing again
Field lines will move towards the field line with zero poloidal field For zero field the field line closes upon it self No magnetic field line can cross this line The field line can not wind around poloidally No flow from top to bottom is possible -> No equilibrium
Poloidal winding of a zero current device with toroidal symmetry
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The stellarator
If the field is not toroidally symmetric the motion in the toroidal direction will move the field line from regions of positive poloidal field into regions of negative field
Then a net poloidal turn of the field line can be achieved Steady state operation is possible at the cost of greater
complexity
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Same thing again
Without toroidal symmetry to toroidal field can move the field line from the region of positive poloidal to negative poloidal field
With the correct shaping of the surfaces one can impose a net transform of the field line
Top and bottom can be connected An equilibrium exists
Poloidal winding of a zero current device without toroidal symmetry
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Large Helical Device (LHD,Japan)
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Stellarator
Inside the device it looks something like this Picture from LHD in JAPAN
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Large Helical Device (LHD,Japan)
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Larges tokamak: JET (EU,UK)
Major radius 3 m Minor radius 1. m Magnetic field < 4 T Plasma volume 100 m3 Plasma current < 7 MA Plasma duration 10 s
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Comparison of confinement time
Confinement times of LHD are below those of the large tokamaks
This is mostly due to the smaller plasma volume
Confinement time of tokamaks and stellarators compared
LHD
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Hellical coils can be simplified
The picture shows how the combination of helical coils and toroidal field coils can be changed to use modular coils
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Applied in W7X
Modular coils of W7x There is a large
disadvantage in the use of the modular coils. They are highly bend and therefore there are large force on them
Also difficult to generate tight aspect ratio machines because the poloidal field decays away from the coils
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Large Helical Device (LHD,Japan)
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Larges tokamak: JET (EU,UK)
Major radius 3 m Minor radius 1. m Magnetic field < 4 T Plasma volume 100 m3 Plasma current < 7 MA Plasma duration 10 s
![Page 26: Physics of fusion power Lecture 10: tokamak - seallarator.](https://reader035.fdocuments.in/reader035/viewer/2022062421/56649d435503460f94a1f48e/html5/thumbnails/26.jpg)
Comparison of confinement time
Confinement times of LHD are below those of the large tokamaks
This is mostly due to the smaller plasma volume
Confinement time of tokamaks and stellarators compared
LHD
![Page 27: Physics of fusion power Lecture 10: tokamak - seallarator.](https://reader035.fdocuments.in/reader035/viewer/2022062421/56649d435503460f94a1f48e/html5/thumbnails/27.jpg)
Compact stellarator NCSX princeton
Compact stellarotors are a challenge. Note there is a plasma current in this device (not driven by a transformed though)
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Tokamak versus stellarator
Advantage of the stellarator Stationary plasma operation No current in the plasma, and therefore no current
driven instabilities
Disadvantage Complex magnetic field coils Curved coils lead to large forces (strong supporting
structures) Difficult to make compact devices
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A tokamak
Plasma (purple) Notice the shape
Surrounded by plates Vessel (pumps) Coils mostly outside vessel
(finite reaction time) Ohmic transformer /
toroidal field coils (green)
Schematic Drawing of the poloidal cross section of the ASDEX Upgrade tokamak
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The tokamak
Magnetic surfaces are the surfaces traced out by the magnetic field
They are nested (best confinement)
Centre is shifted outward Large passive coils Magnetic field ends on a
set of plates Large set of small coils for
diagnostic purposes
Schematic Drawing of the poloidal cross section of the ASDEX Upgrade tokamak
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Pitch of the field
Along the magnetic field
Consequently the length of the field line in toroidal direction is
Pitch of the field line
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Pitch of the magnetic field
Length of the field
In one poloidal turn
Number of toroidal turns in one poloidal turn (safety factor q)
Definition of the minor r and major R radius
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Kink stability
Relation with the current
For stable operation the safety factor at the edge is chosen q > 3. The means a maximum current
Stability considerations of the screw-pinch also apply to the tokamak
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Ratio of poloidal and poloidal field
From the safety factor it follows
Therefore the ratio between the poloidal and toroidal field is
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Pressure and current
From the force balance
Taking the inner product with the magnetic field
The pressure gradient is perpendicular to the surface
Pressure is constant on a surface
Pressure is constant on the magnetic surface, and the current lies inside the surface
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Pressure and current
Again using the force balance
Taking the cross product with the magnetic field
Since the pressure gradient is perpendicular to the surface the current lies inside the surface
Pressure is constant on the magnetic surface, and the current lies inside the surface
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Poloidal flux
The poloidal flux (R,z) is the flux through the circle with its centre at r = 0 lying in the z-plane and having (R,z) lying on its boundary
Integrated over a volume enclosed by two of these circles and the magnetic surface yields The poloidal flux is the flux through the
blue areas. It is constant on a magnetic surface
Point (R,z)
(R2,z2)
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Magnetic surfaces
Traced out by the magnetic field The pressure is constant on the surface The current lies inside the surface The poloidal flux is constant on a surface. The
surfaces are therefore also called flux-surfaces