The present disclosure relates to a magnetic mirror machine for plasma confinement.
Great efforts are being made to design a reactor for controlled fusion on earth. The most promising fusion process is between the hydrogen isotopes deuterium (2H) and tritium (3H). In the deuterium-tritium fusion processes, a 4He alpha particle, having a kinetic energy of about 3.5 MeV and a neutron, having a kinetic energy of about 14.1 MeV, are created.
For fusion to occur, nuclei must be in the form of a plasma having a temperature in the order of 150 million kelvins. Providing confinement for such a plasma remains a major challenge.
Plasma confinement involves confining the charged particles of the plasma. There are several different known magnetic configurations for plasma confinement. A well-known design is the magnetic mirror. Therein, particles follow magnetic field lines, typically running substantially longitudinally through the magnetic mirror machine, and are reflected in areas of increasing magnetic flux density at the respective ends of the device. In other words, the plasma confinement area of the magnetic mirror machine is at each of its two ends limited by a respective mirror area of increased magnetic flux density relative to a central area of the plasma confinement area.
Superconductor coils are well-known for being able to carry large electric currents, thereby, due to Ampere's law, being capable of generating large magnetic flux densities. Limiting factors in the design and use of a superconductor coil with respect to the maximum achievable usable magnetic flux density as generated by the coil include, firstly, the maximum electric current density possible in the superconductor material before breakdown of its superconducting properties, and, secondly, the maximum magnetic flux density possible in the superconductor material itself before breakdown of its superconducting properties.
Thus, there is a need to maximize the performance of a magnetic mirror machine given the above design constraints.
It is an object of the present disclosure to solve, or at least mitigate, the above problem.
To this end, according to a first aspect, there is provided a magnetic mirror machine for plasma confinement, comprising a plurality of longitudinally disposed superconductor coils arranged for producing an open-field-line plasma confinement area, said plasma confinement area at each of two ends being limited by a respective mirror area of increased magnetic flux density relative to a central area of said plasma confinement area, wherein a superconductor coil of said of plurality of superconductor coils is located adjacent to said mirror area and said superconductor coil has a cross-section, in a plane intersecting a magnetic field line through said mirror area, having an elongate shape in a direction along said magnetic field line.
As the cross-section having an elongate shape should be understood as having an extension, in a first major direction of the cross-section, being at least twice, more preferably three times, even more preferably four times, and even more preferably five times an extension in a second major direction of the cross-section. An elongate shape should be understood as include, but not being limited to, a rectangular, elliptical, crescent-shaped, and/or tubular-segment-shaped cross-section. The first and second major directions may be orthogonal to each other, but the second direction may also be curved, i.e., having a curved shape with respect to the first direction, as would be the case with a tube-shaped cross section.
As a direction along the magnetic field line should be understood as a direction more parallel to the magnetic field line than perpendicular to the magnetic field line. In particular, the direction along the magnetic field line may be parallel or substantially parallel to the magnetic field line.
The present inventive concept stems from a realization that the arranging of the superconductor coil with an elongate cross-section in a direction along a magnetic field line in the mirror area may allow for maximizing the maximum magnetic flux density in the mirror areas of the magnetic mirror machine, given the design constraints of a maximum allowable magnetic flux density within the superconductor coil and a maximum coil current density.
In turn, a high magnetic flux density in the mirror areas may allow for a high mirror ratio in the magnetic mirror machine, i.e., a high ratio between the maximum magnetic flux density in a mirror area and the magnetic flux density in a central area of the magnetic mirror machine, which thereby may reduce the size of the loss cone and allow for better confinement of a plasma.
A high magnetic flux density in the mirror areas may allow for a high total magnetic flux in the magnetic mirror machine.
Thus, through the present inventive concept, there is provided a magnetic mirror machines comprising superconductor coils, maximizing the magnetic flux density in the mirror areas, given the design constraints of the super-conducting coils.
Alternatively or additionally, the high magnetic flux density in the mirror areas may allow for a high product of magnetic flux density in and radius in the central area of the magnetic mirror machine.
A perimeter segment of said cross-sectional area directed towards said mirror area may convex as seen from outside said perimeter segment. Alternatively, or additionally, the perimeter segment may be curved in a same direction as a magnetic field line in the mirror area. This may allow for further maximizing of the maximum magnetic flux density in the mirror areas.
A perimeter segment of said cross-sectional area directed away from said mirror area may be concave as seen from outside said perimeter segment. Alternatively, or additionally, the perimeter segment may be curved in a same direction as a magnetic field line in the mirror area. This may allow for further maximizing of the maximum magnetic flux density in the mirror areas.
The perimeter segment of said cross-sectional area directed towards said mirror area runs may run parallel to the perimeter segment of said cross-sectional area directed away from said mirror area. This may allow for further maximizing of the maximum magnetic flux density in the mirror areas.
The plurality of superconductor coils may be disposed co-axially and longitudinally spaced and each arranged for carrying respective currents in a same direction. This is a particularly beneficial application of the present inventive concept.
The plurality of superconductor coils may comprise a first magnet system comprising a first plurality of concentrically arranged circular-loop superconductor coils, comprising a first superconductor coil arranged to carry a current in a first direction; and a second superconductor coil arranged to carry a current in a second direction opposite to said first direction; and a second magnet system comprising a second plurality of concentrically arranged circular-loop coils, arranged with mirror symmetry with respect to said first magnet system relative to a symmetry plane located between said first magnet system and said second magnet system. This is another particularly beneficial application of the present inventive concept.
The plurality of superconductor coils may further comprise a third magnet system arranged radially outside said plasma confinement area, said third magnet system comprising at least one superconductor circular-loop coil.
According to another aspect, there is provided a fusion reactor comprising the magnetic mirror machine of the first aspect. This aspect may generally present the same features and advantages as the first aspect.
According to another aspect, there is provided use of the magnetic mirror machine of the first aspect in a fusion reactor. This aspect may generally present the same features and advantages as the first aspect.
The above, as well as additional objects, features and advantages of the present disclosure, will be better understood through the following illustrative and non-limiting detailed description of preferred embodiments, with reference to the appended drawings, where the same reference numerals will be used for similar elements, wherein:
As is generally known, plasma confinement devices may be based either on open magnetic field lines or closed field lines.
A closed-field-line configuration may, for example, be realized with a toroidal magnetic field. An example of such a device is a tokamak.
Open-field-line plasma confinement devices, as known in the prior art, may operate by a principle of magnetic mirroring, wherein the charged particles of the plasma are reflected in areas of increasing magnetic flux density at the respective ends of the confinement area.
While recognized to be able to provide plasma confinement, open-field-line plasma confinement devices will always have leakage of charge particles with velocity vectors sufficiently aligned with the magnetic field lines. More specifically, the mirror effect will occur for all particles within a range of angles of approach outside a loss cone defined by the helix spiral pitch angle of the charged particle's gyration spin around the magnetic field lines.
The extent of the loss cone is determined by the mirror ratio rmirror, defined as the ratio between the maximum magnetic flux density at the mirror area Bmirror and the minimum magnetic flux density Bcentral in a central area of the magnetic mirror machine, following a magnetic field line:
The angle defining the loss cone is then:
Thus, it can be seen that high mirror ratio will lead to a small loss cone, so that only the particle having velocities the most aligned with the field lines will escape. Conversely, a low mirror ratio will lead to a larger loss cone.
The superconductor coils throughout this disclosure may be manufactured and arranged using methods, materials, compounds, and the like, known per se in the art.
Suitable superconductor materials may include YBCO, Bi2223, 2212, Nb3SN, NbTi and/or MgB2.
The superconductor coils throughout this disclosure may, for example, be so-called high-temperature superconductor coils. As known in the art, a superconductor coil may comprise internal structure. For example, within each superconductor coil, superconducting material may be arranged in filaments, strands, cables, ropes, or the like. using methods generally known in the art. The cross-section of the coil, as referred to throughout this disclosure, should then be understood as an enclosing envelope of this internal structure.
For example, the superconductor coils throughout this disclosure may be manufactured and arranged using methods, materials, compounds, and the like, as detailed in D Uglietti: A review of commercial high temperature superconducting materials for large magnets: from wires and tapes to cables and conductors, Supercond. Sci. Technol. 32 (2019) 053001 (29pp), https://doi.org/10.1088/1361-6668/ab06a2, incorporated herein by reference.
Further, the superconductor coils may be cooled using methods generally known per se in the art.
The magnetic mirror machine 2100 may be used for plasma confinement, and may comprise customary shielding 2102, for example neutron shielding 2102, as known in the art. In particular, the magnetic mirror machine 2100 may be comprised in a fusion reactor and/or used in a fusion reactor.
As evident from
The plasma confinement area 2106 thus extends in a longitudinal direction of the magnetic mirror machine 2100, along the symmetry axis A, through the magnetic mirror machine 2100, with the magnetic field lines 2112 running along the longitudinal direction as well.
In the configuration of
The plasma confinement area 2106 is at each of two ends limited by a respective mirror area 2108 of increased magnetic flux density relative to a central area 2110 of the plasma confinement area 2106, as is evident from the magnetic field line spacing in each mirror area 2108 and the central area 2110, and as known per se in the art.
A respective superconductor coil 2105 of the plurality of superconductor coils 2105, 2106 is located adjacent to each respective mirror area 2108. Indeed, in the example of
As is evident from
Alternatively, as also evident from
In the example of
Thus, the cross section of each superconductor coil 2105 is such that a perimeter segment 2307a of the cross-sectional area directed towards the mirror area 2108 is convex as seen from outside the perimeter segment 2307a.
Moreover, a perimeter segment 2307b of the cross-sectional area of each superconductor coil 2306 directed away from the mirror area is concave as seen from outside the perimeter segment 2307b.
Naturally, other curved cross sections are equally possible, not necessarily following a circular segment path, with convex and concave perimeter segments, as per the previous two paragraphs.
Further, in the example of
Magnetic field simulations were performed to evaluate the designs of the magnetic mirror machine 2100 of
Table 1 shows results of the simulations, wherein:
The simulations were performed using a wall 2102 thickness of 700 mm, an initial magnetic mirror machine inner radius R at the symmetry plane P of 3 300 mm, and a distance between the symmetry plane P and the coils 2105 of 5 000 mm.
The simulations were performed assuming a constant current density within each superconductor coil and with a constraint that the maximum magnetic flux density within each coil 2105 adjacent to the mirror area 2108 must not exceed approximately 23 T, being a typical value for a breakdown magnetic flux density for the respective superconductor coil.
Further, the radius of each magnetic mirror machine was varied so that the product Bcentral, avg×R of the average magnetic flux density Bcentral, avg at the symmetry plane P and the inner radius R of the magnetic mirror machine, the latter thus roughly corresponding to the radius of the plasma confinement area 1206 at the symmetry plane P, was fixed at 6.0 T m.
In the results of Table 1, reflecting the above-mentioned design constraint, Bcoil is in each case is close to 23 T. It should be noted that due to the linear nature of magnetic fields, the present results may be readily be scaled to other coil maximum magnetic flux densities than 23 T, for which the results are equally valid.
As can be seen from Table 1, the elongate coil cross section in the magnetic mirror machine 2200 allows for a higher magnetic flux density Bmirror in the mirror area, given the constraint of not exceeding a magnetic flux density of approximately 23 T in the coil, as compared to the circular non-elongate coil 2105 of the magnetic mirror machine 2300 of
The magnetic flux density Bcentral, outer of the central area remains roughly constant in each magnetic mirror machine. Thus, the increased Bmirror in
The present inventive concept is equally applicable to a magnetic mirror machine wherein the plurality of superconductor coils comprises a first magnet system comprising a first plurality of concentrically arranged circular-loop superconductor coils, comprising a first superconductor coil arranged to carry a current in a first direction; and a second superconductor coil arranged to carry a current in a second direction opposite to the first direction; and a second magnet system comprising a second plurality of concentrically arranged circular-loop coils, arranged with mirror symmetry with respect to the first magnet system relative to a symmetry plane located between the first magnet system and the second magnet system, the concept of and advantages of which being discussed in detail elsewhere in this disclosure.
The magnetic mirror machine 3100 is rotationally symmetric, or at least substantially rotationally symmetric, around a symmetry axis A.
The magnetic mirror machine 3100 may be used for plasma confinement, and may comprise customary shielding 2102, for example neutron shielding 2102, as known in the art. In particular, the magnetic mirror machine 2100 may be comprised in a fusion reactor and/or used in a fusion reactor.
As evident from
The plasma confinement area 2106 thus extends in a longitudinal direction, along the symmetry axis A, through the magnetic mirror machine 3100, with the magnetic field lines 2112 in the plasma confinement area 2106 running in the longitudinal direction as well.
In particular, superconductor coils 2206a and 2206b located above the symmetry plane P constitute a first magnet system, wherein the coil 2206a is arranged to carry a direct current in a first direction and the coil 2206b is arranged to carry a direct current in a second, opposite, direction, as indicated with dots and crosses in
Further, the superconductor coils 2206a and 2206b located below the symmetry plane P constitute a second magnet system, arranged with mirror symmetry with respect to the first magnet system relative to the symmetry plane P, which thus is located between the first magnet system and the second magnet system.
Through such an arrangement, an annular confinement area 2106 may be created, as detailed elsewhere in this disclosure.
Further, a third magnet system comprising at least one superconductor coil, typically a plurality of superconductor coils, and in the example of
The plasma confinement area 2106 is at each of two ends limited by a respective mirror area 2108 of increased magnetic flux density relative to a central area 2110 of the plasma confinement area 2106, as is evident from the magnetic field line spacing in each mirror area 2108 and the central area 2110.
The superconductor coils 2206a, 2206b of the first magnet system and of the second magnet system are located adjacent to the respective mirror area 2108. In the example of
As is evident from
Thus, each of the superconductor coils 2206a, 2206b adjacent to each respective mirror area 2108 has a crescent-shaped cross section. In particular, the cross section of each superconductor coil is such that a perimeter segment 2207a of the cross-sectional area directed towards the mirror area 2108 is convex as seen from outside the perimeter segment 2207a.
Alternatively, as also evident from
Further, as shown in the example of
Other elongate cross sections, such as a rectangular one as in
The magnetic mirror machine 3200 has the same features as the magnetic mirror machine 3100 of
Thus, the cross section of each superconductor coil is such that a perimeter segment 2207a of the cross-sectional area directed towards the mirror area 2108 is convex as seen from outside the perimeter segment 2207a.
Moreover, a perimeter segment 2207b of the cross-sectional area of each superconductor coil 2306 directed away from the mirror area is concave as seen from outside the perimeter segment 2207b.
Naturally, other curved cross sections are equally possible, not necessarily following a circular segment path, with convex and concave perimeter segments, as per the previous two paragraphs.
Further, in the example of
Magnetic field simulations were performed to evaluate the designs of the magnetic mirror machine 3100 of
Table 2 shows results of the simulations, wherein:
Bcoil is the maximum magnetic flux density within each coil 2206a, 2206b adjacent to the mirror area 2108,
The simulations were performed using a wall 2102 thickness of 700 mm, a magnetic mirror machine inner radius R at the symmetry plane P of 3 300 mm, and a distance between the symmetry plane P and the coils 2206a, 2206b of 5 000 mm.
The simulations were performed assuming a constant current density within the superconductor coil and with a constraint that the maximum magnetic flux density within each coil 2105 adjacent to the mirror area 2108 must not exceed approximately 23 T, being a typical value for a breakdown magnetic flux density for the respective superconductor coil.
Further, the radius of each magnetic mirror machine was varied so that the ratio Bcoil/Bmirror was maximized, being equivalent to maximizing Bmirror due to the constant Bcoil.
In the results of Table 2, reflecting the above design constraint, Bcoil is in each case 23.0 T. It should be noted that due to the linear nature of magnetic fields, the present results may be readily be scaled to other coil maximum magnetic flux densities than 23.0 T, for which the results are equally valid.
As can be seen from Table 2, the elongate crescent-shaped coil cross sections in the magnetic mirror machine 3100 allow for a higher magnetic flux density Bmirror in the mirror area, given the constraint of not exceeding a magnetic flux density of approximately 23 T in the coil, as compared to the circular non-elongate coil 2206a, 2206b of the magnetic mirror machine 3300 of
Thus, in the present optimization, the magnetic flux density Bcentral, outer of the central area remains around 7-8 T, while the elongate and tubular segment cross-sections allow for a considerably increased product Bcentral, avg R.
The inventive concept has mainly been described above with reference to example embodiments. However, as is readily appreciated by a person skilled in the art, other embodiments than the ones disclosed above are equally possible within the scope of the inventive concept, as defined by the appended patent claims. In particular, other elongate cross-sections than those specifically discussed herein are equally possible, within the scope of the claims. In particular, crescent-like cross sections such as the one of
The remainder of this disclosure relates to a plasma confinement device and to a method for plasma confinement.
Great efforts are being made to design a reactor for controlled fusion on earth. The most promising fusion process is between the hydrogen isotopes deuterium (2H) and tritium (3H). In the deuterium-tritium fusion processes, a 4He alpha particle, having a kinetic energy of about 3.5 MeV and a neutron, having a kinetic energy of about 14.1 MeV, are created.
For fusion to occur, nuclei must be in the form of a plasma having a temperature in the order of 150 million kelvins. Providing confinement for such a plasma remains a major challenge.
There are several different known magnetic configurations for plasma confinement.
Plasma confinement involves confining the charged particles of the plasma. Further, various properties beneficial to the stability of the confined plasma may be desirable.
A well-known design is the magnetic mirror. Therein, particles follow magnetic field lines and are reflected in areas of increasing magnetic flux density at the respective ends of the device. While capable of plasma confinement, as has been demonstrated experimentally, it is associated with various plasma instability problems. To solve these problems, various convoluted non-rotationally symmetric geometries have been proposed in the prior art, such as the “Minimum B” design, resembling a tennis ball, or the “Biconic Cusp”.
Another well-known design is the tokamak. The tokamak uses a toroidal, i.e., donut-shaped, field for confinement. The tokamak, too, is associated with various plasma stability problems, such as charge separation.
It is an object of the present disclosure to provide an improved plasma confinement device and method, in particular for use in fusion reactors.
To this end, according to a first aspect, there is provided a plasma confinement device, comprising a first magnet system, comprising a first plurality of concentrically arranged circular-loop coils, comprising a first coil arranged to carry a current in a first direction, and a second coil arranged to carry a current in a second direction opposite to the first direction; and a second magnet system comprising a second plurality of concentrically arranged circular-loop coils, arranged with mirror symmetry with respect to the first magnet system relative to a symmetry plane located between the first magnet system and the second magnet system, creating an annular plasma confinement area at the symmetry plane with a magnetic field normal to the symmetry plane at the symmetry plane.
As an annular plasma confinement area should be understood a rotationally symmetric region in which the charged particles of the plasma are confined, including cases having, for example, a donut-like or disc-like topology.
Hereby, the resulting magnetic field configuration may confine charged particles using static axial and radial fields in an open-field-line magnetic mirror configuration.
The arrangement with the first coil being arranged to carry a current in a first direction and the second coil being arranged to carry a current in an opposite, second, direction, in each of the first magnet system and the second magnet system, allows for the creation of a region of high magnetic flux density between the first coil and the second coil, while maintaining a relatively lower flux density near the symmetry plane. Compared to a conventional magnetic mirror arrangement, this allows for an increased mirror ratio, thereby reducing the size of the loss cone and allowing for better confinement of the plasma.
Moreover, compared to a tokamak, when confining a plasma, the charge separation effects may be avoided, where no induced plasma current may be needed for stability of the plasma. With the resulting quasi-static plasma, i.e., without a global plasma current, one may in turn avoid magnetohydrodynamic instabilities. Further, a fusion reactor may be allowed to run in a continuous (steady) state without current ramping.
Further, the resulting magnetic field configuration may allow for an uncomplicated way of heating the plasma.
The first plurality of concentrically arranged coils may, for example, be identically designed to the second plurality of concentrically arranged coils. This is a particularly simple way of achieving the desired magnetic field configuration.
The device may further comprise a third magnet system arranged radially outside the plasma confinement area, the third magnet system comprising at least one circular-loop coil.
Hereby, it is possible to arrange for a strictly radially increasing magnetic field, which may be beneficial for the stability of the confined plasma, further improving on a conventional magnetic mirror.
Further, the arrangement with a third magnet system may allow for arranging a concave magnetic field in the whole plasma confinement area, which may be beneficial for the stability of the confined plasma.
Thus, a rotationally symmetric open-field-line plasma confinement device may be provided that has a high mirror ratio and has properties beneficial for plasma stability.
Moreover, the third magnet system may allow controlling a confined plasma by current adjustment in the circular-loop coil of the third magnet system.
The third magnet system may comprise a first coil arranged on a same side of the symmetry plane at the first magnet system and a second coil arranged on an opposite side of the symmetry plane, wherein the second coil is arranged with mirror symmetry relative to the first coil.
The first plurality of concentrically arranged coils in the first magnet system and the second plurality of concentrically arranged coils in the second magnet system may each be embedded in respective ferromagnetic structures. This increases the magnetic flux through the relatively higher permeability of the ferromagnetic material, leading to a stronger magnetic field, and thereby better confinement, for a given coil current.
Optionally, a said ferromagnetic structure does not cover at least one coil of a respective said plurality of coils in a direction towards said symmetry plane. This shields magnetic flux in the direction away from the symmetry plane and directs the magnetic flux in the direction towards the symmetry plane, i.e., towards the plasma. Thereby, more efficient shielding is achieved for a given coil current.
A said ferromagnetic structure may be ferromagnetic steel.
The device according to the first aspect may be used for confining a plasma.
The device according to the first aspect may be used in a fusion reactor.
According to a second aspect, there is provided a method of plasma confinement, comprising, in a first magnet system, comprising a first plurality of concentrically arranged circular-loop coils, a first coil carrying a current in a first direction and a second coil carrying a current in a second direction opposite to the first direction; and a second magnet system comprising a second plurality of concentrically arranged circular-loop coils carrying currents with mirror symmetry with respect to the first magnet system relative to a symmetry plane located between the first magnet system and the second magnet system, creating an annular plasma confinement area at the symmetry plane with a magnetic field normal to the symmetry plane.
Embodiments and advantages of this second aspect may generally be similar to or the same as those of the first embodiment.
The method may further comprise controlling a confined plasma by current adjustment in a third magnet system arranged radially outside the plasma confinement area.
The controlling may comprise changing the radius of the plasma confinement area, which thereby, in turn, may change the radius of the plasma.
The method may further comprise heating the plasma by inserting an ion beam in an area radially outside the plasma confinement area or radially inside the plasma confinement area and allowing ions from the ion beam to drift into the plasma confinement area.
In contrast to existing solutions—such as Tokamaks or similar devices, where the magnetic field created to confine the plasma also deflects ions coming from outside from the plasma, and heating needs to be performed using neutral beams that will penetrate though the magnetic field and then only get ionized once inside the plasma—here, high-energy ions may conveniently and simply be added to the confined plasma, or provided for initial heating of the plasma to create a fusion condition, since the present magnetic field configuration may pull the ions into the plasma confinement area, rather than deflect them. This may lead to a less complicated procedure and may further reduce particle losses.
According to a third aspect, there is provided a magnetic mirror machine and/or a particle confinement device, comprising a first magnet system, comprising a first plurality of concentrically arranged circular-loop coils, comprising a first coil arranged to carry a current in a first direction, and a second coil arranged to carry a current in a second direction opposite to the first direction; and a second magnet system comprising a second plurality of concentrically arranged circular-loop coils, arranged with mirror symmetry with respect to the first magnet system relative to a symmetry plane located between the first magnet system and the second magnet system, creating an annular particle confinement area at the symmetry plane with a magnetic field normal to the symmetry plane at the symmetry plane.
Embodiments and advantages discussed in conjunction with the other aspects, and throughout this disclosure, are compatible with this third aspect.
According to a fourth aspect, there is provided a method of confining charged particles, comprising, in a first magnet system, comprising a first plurality of concentrically arranged circular-loop coils, a first coil carrying a current in a first direction and a second coil carrying a current in a second direction opposite to the first direction; and a second magnet system comprising a second plurality of concentrically arranged circular-loop coils carrying currents with mirror symmetry with respect to the first magnet system relative to a symmetry plane located between the first magnet system and the second magnet system, creating an annular particle confinement area at the symmetry plane with a magnetic field normal to the symmetry plane.
Embodiments and advantages discussed in conjunction with the other aspects, and throughout this disclosure, are compatible with this third aspect.
As is generally known, plasma confinement devices may be based either on open magnetic field lines or closed field lines.
Closed-field line devices may, for example, have a toroidal magnetic field. An example of such a device is a tokamak.
Closed-field-line devices may potentially confine plasma particles without leakage, as the particles will follow the field lines, but other issues, such as E×B drift due to charge separation and magneto-hydrodynamic (MHD) effects may cause a plasma to escape. Special arrangements need to be made for removing helium ash, such as pulsing the system, disallowing steady-state operation.
One major problem with the toroidal field is that ions will escape confinement due to E×B drift caused by charge separation.
In a tokamak, this problem may be addressed by inducing a current in the plasma, where the current will create a poloidal field. This results in the magnetic field twisting along the torus, with poloidal and toroidal fields together making up the twisted magnetic field. This mitigates the E×B drift but introduces an additional problem in that the plasma only will be confined while the current in the inner magnetic coil is ramping up, i.e. it is not possible to run in steady state.
Further, the plasma current will result in several instabilities related to magnetohydrodynamic effects, such as Kink instabilities. This may be addressed by various compensation coils around the reactor vessel, but the basic characteristics of the plasma will still be unstable due to the large magnetohydrodynamic effects.
Open-field-line plasma confinement devices, as known in the prior art, may operate by a principle of magnetic mirroring, wherein the charged particles of the plasma are reflected in areas of increasing magnetic flux density at the respective ends of the confinement area. Such machines have the ability of steady-state operation, and may generally have less problems with charge separation, and also allow for easier handling of helium ashes.
While recognized to be able to provide plasma confinement, open field-line plasma confinement devices will always have leakage of charge particles with velocity vectors sufficiently aligned with the magnetic field lines. More specifically, the mirror effect will occur for all particles within a range of angles of approach outside a loss cone defined by the helix spiral pitch angle of the charged particle's gyration spin around the magnetic field lines.
The extent of the loss cone is determined by the mirror ratio rmirror, defined as the ratio between maximum Bmax and minimum Bmin magnetic flux density following a magnetic field line:
The angle defining the loss cone is then:
Thus, it can be seen that high mirror ratio will lead to a small loss cone, so that only the particle having velocities the most aligned with the field lines will escape. Conversely, a low mirror ratio will lead to a larger loss cone.
A first property, known from literature, of the magnetic field lines of a plasma confinement device, associated with magneto-hydrodynamic stability of the confined plasma, is a concave magnetic field, i.e., a magnetic field having concave magnetic field lines, as seen from outside the plasma confinement area and the confined plasma.
A second property, known from literature, of the magnetic field lines of a plasma confinement device, associated with magneto-hydrodynamic stability of the confined plasma, is a radially strictly increasing magnetic field.
The first magnet system 1 comprises a first plurality of concentrically arranged circular-loop coils arranged around a symmetry axis A, for example, as shown a first, inner coil 11 and a second, outer, coil 12, arranged concentrically to radially outside the inner coil 11.
Further, the first magnet system 1 comprises a second magnet system 2 comprising a second plurality of circular-loop coils, likewise concentrically arranged around the axis A, but vertically displaced relative to the first magnet system. The second magnet system may, for example, as shown, comprise a first, inner coil 21 and a second, outer, coil 22, arranged concentrically to and radially outside the inner coil 21.
The coils 21, 22 of the second magnet system 2 are arranged with mirror symmetry with respect to the coils 11, 12 of first magnet system 1 relative to a symmetry plane P, which is at equal distance to each of the first magnet system 1 and to the second magnet system 2.
Throughout this disclosure, reference may be made to coordinate systems and directions relative to the axis A and the symmetry plane P. In particular, coordinates and directions may be described with reference to a cylindrical coordinate system or to a cartesian coordinate system, each having as origin the intersection of the symmetry axis A and the symmetry plane P.
The cartesian coordinate system, with coordinates referred to as “x, y, z”, “X, Y, Z”, “A, B, C” or the like, should be understood as having the first two coordinate axes “x, y”, “X, Y”, “A, B”, or the like, lying in the symmetry plane P and the third coordinate axis “z”, “Z”, “C”, or the like, extending in a positive direction upwards (as seen in
If no units for spatial coordinates are disclosed, units of meters or degrees are implied. If no unit of time is disclosed, a unit of seconds is implied.
The cylindrical coordinate system, should be understood as having a radial direction and coordinate (“R”, “r”, or the like) extending from the origin at the intersection of the symmetry axis A and the symmetry plane P, an azimuth direction and coordinate (“phi”, “Phi”, or the like) measured as a rotational angle around the symmetry axis A, and an axial direction and coordinate (“z”, “Z”, “C” or the like) extending in a positive direction from the origin upwards along the symmetry axis A. Positive direction for the azimuth direction is according to the right-hand rule with respect to the positive axial direction.
Further, throughout this disclosure references will be made to figures showing simulated magnetic field (magnetic flux density) lines, i.e., equal magnetic potential lines, including
Still with reference to
In the first magnet system 1, the current of the inner coil 11 is configured to run in a direction into the cross-sectional plane (marked with a cross) on the right side of
Thus, the first plurality of concentrically arranged circular-loop coils comprises a first coil 11 arranged to carry a current in a first direction, and a second coil 12 arranged to carry a current in a second direction opposite to the first direction.
Similarly, respecting the mirror symmetry with respect to the symmetry plane P, in the second magnet system 2, the current of the inner coil 21 is configured to run in a direction into the cross-sectional plane (marked with a cross) on the right side of
Thus, the currents of the second magnet system 2, with first magnet system 1 and the second magnet system 2 in operation, are arranged with mirror symmetry with respect to the first magnet system relative to the symmetry plane P located between the first magnet system 1 and the second magnet system 2.
As shown with a vector arrow 202 indicating the magnetic field (magnetic flux density) vector B, at the symmetry plane P, the mirror-symmetric configuration of currents in the first magnet system 1 and the second magnet system 2 creates, at the symmetry plane P, a magnetic field normal to the symmetry plane P. An annular, typically toroid-shaped, plasma confinement area 206 (cf.
Thus, expressed in other words, a plasma confinement device may comprise two disc-shaped magnet systems 1, 2 facing each other in axial direction, with a space in-between where a plasma may be confined. Each magnet system 1, 2 has at least two coils 11, 12, 21, 22 where the current direction and magnitude create a normal magnetic field boundary condition at the symmetry plane P.
Further, still with reference to
Optionally, as shown, the respective core structures 204 of the first magnet system 1 and the second magnet system 2 do not cover at least one coil, as shown all coils of the respective plurality of coils in a direction towards the symmetry plane P, but covers the respective coils 11, 12, 21, 22 in all other directions.
For comparison purposes,
The disclosed magnet system configurations makes the magnetic field normal to the symmetry plane P throughout the symmetry plane P, as is evident by the magnetic field lines crossing the symmetry plane P at right angles.
In
Unlike the situation in a tokamak, where the plasma is confined with toroidal and poloidal fields, a confinement device according to the present disclosure confines plasma with axial (parallel to the axis A) and radial fields.
Just as discussed above in conjunction with
Moreover, as is evident from comparing
Further, the third magnet system 3 may, as shown, be located radially outside, with respect to the axis A, the first magnet system 1 and the second magnet system 2.
The third magnet system 3 comprises at least one circular-loop coil, for example, as shown, a first circular-coil loop coil 31 arranged on the same side of the symmetry plane P as the first magnet system and a second circular-coil loop 32 arranged on the opposite side of the symmetry plane P, wherein the second coil 32 is arranged with mirror symmetry relative to the first coil 31. In particular, with reference to
Resulting simulated magnetic field lines are shown in
Still with reference to
Moreover, still with reference to
Moreover, still with reference to
Furthermore, as evident from
Further, each plasma confinement device 500 comprises a plasma vessel 208, as well-known per se in plasma fusion technology. The plasma vessel may, as shown be located between the first magnet system 1 and the second magnet system 2. Further, the plasma vessel 208 may, as shown, be located radially inside the third magnet system 3, if such a system is present. The plasma vessel 208, may as shown, be rotationally symmetric around the axis A. The reactor vessel 208 is located so that the annular, toroid-shaped, plasma confinement area 206 is located inside the reactor vessel 208.
Physical dimensions of the plasma confinement device 500 depend on many parameters such as engineering current density in the magnetic coils, the degree of confinement of alpha particles, the desired plasma volume, etc. Below follow typical dimensions that may provide good confinement of alpha particles and a plasma volume of roughly 15 m3 at an engineering current density in the magnet systems of 10 A/mm2:
Outer diameter the first magnet system 1 and the second magnet system 2: 8 m-16 m, typically 12 m.
Height of each of the coils 11, 12, 21, 22: 1.5 m-3.5 m, typically 2.5 m
Thickness of the core 204 embedding coils: 0.6 m-1.3 m, typically 1.0 m.
Distance between the upper edge of the first magnet system 1 and the lower edge of the second magnet system 2: 4.0 m-8.0 m, typically 6.0 m
Outer diameter of the third magnet system 3: 10.0 m-22 m, typically 16.0 m.
By varying the coil current or coil current the magnetic field configuration may be changed as to control a plasma confined in the plasma confinement area 206. For example, the radius of the plasma confinement area may be changed.
Further, the plasma confinement device 500 may have an optional ion beam insertion arrangement 212, as known per se, leading into the vessel 208 and being located radially outside the plasma confinement area 206.
An ion beam, for example comprising high-energy alpha particles, may be inserted using the ion beam insertion device 210 in an area radially outside the plasma confinement area 206, after which ions from the ion beam may be allowed to drift towards lower radius into the plasma confinement area 206, thereby heating the plasma, which may in the next phase be self-sustaining in heating, i.e. ignited plasma.
Alternatively (not shown) an ion beam, for example comprising high-energy alpha particles, may be inserted using such an ion beam insertion device in an area radially inside the plasma confinement area 206, after which ions from the ion beam may be allowed to drift towards higher radius into the plasma confinement area 206, thereby heating the plasma.
Thus, the plasma confinement device design according to the present disclosure allows accessibility for heating devises both at the outer radius and at the center of the system.
Alternatively, again, the plasma may be heated by the microwave plasma heating device 210.
Further,
Typical dimensions may be as follows. Including the housing 1500, the device 500 may have diameter of about 25 m and a height of about 35 m. The inner diameter of the coils of the third magnet system 3 may be about 12 m. The minimal distance between the inner coils 11, 21 of, respectively, the first magnet system 1 and the second magnet system 2, may be about 11 m.
According to the present disclosure, the overall current in a system of particles, i.e., plasma, confined therein may be zero, or close to zero. This may result in a much less dynamic plasma compared to the toroidal based reactors, such as tokamaks. Such a less dynamic plasma may have less problems with current-driven plasma instabilities, such as kink instability.
In the following, simulation results for a plasma confinement device according to the present inventive concept will be discussed, with reference to
If an alpha particle can be confined, it will contribute to the heating of the plasma so that an ignited plasma is self-sustained by confined alpha particles. Burning plasma needs external energy, but less than the heating energy produced by the fusion process. Such heating is provided by fusion-product alpha-particles. Thus, confining alpha particles is important.
Deuterium and tritium will fuse at 12 keV or even lower. To confine a lighter ion at a lower energy is much easier than the heavy ion at high energy. If fusion-product alpha particles may be confined, deuterium and tritium ions as well as the electrons will also be confined in the same volume, i.e., if the alpha particles are confined, deuterium and tritium ions will also be confined.
Simulations were performed of trajectories of charged particles with in a magnetic field computed by finite element method (FEM) simulation, verifying the capability of charged particle confinement.
Since the system is rotationally symmetric, it could be described in a two-dimensional (2D) simulation. Furthermore, since there is mirror symmetry between the two first magnet system and the second magnet system, a first quadrant (cf.
Particle trajectories were calculated iteratively, taking into account the Lorentz force on the particle and Newton's second law.
The inventive concept has mainly been described above with reference to example embodiments. However, as is readily appreciated by a person skilled in the art, other embodiments than the ones disclosed above are equally possible within the scope of the inventive concept, as defined by the appended patent claims.
The following are examples forming part of the description.
Number | Date | Country | Kind |
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PCT/EP2020/081762 | Nov 2020 | WO | international |
Filing Document | Filing Date | Country | Kind |
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PCT/EP2021/081409 | 11/11/2021 | WO |