• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    A toroidal plasma device has a toroidal confinement vessel defining a toroidal space and confining ionized gas therein. A solenoid which links the toroidal space induces a toroidal electric field therein to produce plasma current. A plurality of first windings are wound substantially helically around the vessel substantially equally spaced around its minor circumference. A plurality of second windings are wound substantially helically around the vessel substantially midway between successive first windings. Direct current is passed through the respective first and second windings in opposite directions with the current in the respective first and second windings equal or slightly unbalanced. The currents in the first and second windings produce a helical magnetic field. The combination of the poloidal magnetic field from the plasma current with this helical magnetic field produces a separatrix in the toroidal space, this separatrix defining a closed surface which limits and encloses a region within which closed and nested magnetic flux surfaces exist. The sense of rotation of the first and second windings and the direction of the plasma current produces a variation in the safety fractor q with minor radius at any poloidal angle, whereby the sign of q reverses near the outer edge of the plasma, q being an average over a flux surface of the number of transit made around the torus in the toroidal direction by a magnetic flux line in making a single transit in the poloidal direction. The sign of q is determined by the sense of the direction in which the toroidal transit is made.
    公开号:SU1217269A3
    申请号:SU792809244
    申请日:1979-09-03
    公开日:1986-03-07
    发明作者:Окава Тахиро
    申请人:Га Текнолоджиз Инк (Фирма)；
    IPC主号:
    专利说明:

    2. Method POP1, characterized in that 4to currents in the spiral windings are created equal
    in magnitude.
    3. A method according to claim 1, characterized in that an external longitudinal magnetic field is applied.
    4. Method according to claim 3, characterized in that the external magnetic field is created to coincide in direction with the current in the plasma cord.
    5. The method according to p. 3, which is that the longitudinal magnetic field is created by changing the ratio of the currents in the spiral windings.
    6. The method according to claim 1, characterized in that the magnitude of the spiral and longitudinal magnetic fields is chosen so that the separatrix magnetic field occupies a position inside the chamber,
    7. Method according to claim 6, characterized in that the current in the cord is changed until the separatrix of the magnetic field takes up a position inside the chamber.
    8. A device for holding and heating a plasma, containing an axisymmetric chamber, means for creating a plasma and maintaining a pulsed axial current in it, and a system of windings for creating external
    The invention relates to controllable thermo-nuclear synthesis and can be used in the development of thermo-nuclear reactors.
    Methods are known for confining and heating a plasma, including creating, maintaining and heating plasma in closed magnetic traps using external magnetic systems, creating currents in the plasma sufficient to heat and retain the plasma by external and internal fields.
    Among the devices realized by the known methods are the device of controlled thermo-nuclear synthesis with toroidal chambers tokamak, stellarator and 2-pin p inverse field.
    217269
    for C1 to the plasma of magnetic fields wound on the chamber, characterized in that the winding system contains the first and second spiral windings wound in one direction with equal pitch and equally displaced one with another along the axis of the chamber, and means are maintained in said windings oppositely directed currents.
    jf
    9. A device according to claim 1, characterized in that a means for independent maintenance of currents in the first and second spiral windings is introduced into it,
    10. A device according to claim 8, characterized in that the windings are wound at an angle of 45 with respect to the axis of the chamber.
    11. The device according to claim 8, characterized in that it comprises two first and two second spiral windings.
    12. The device according to claim 8, characterized in that it comprises three first and three second spiral windings.
    13. The device according to claim 8, characterized in that the chamber is filled with a toroidal configuration IfVl.
    In tokamaks, the toroidal current is created by a transformer, the gas held in the toroidal chamber serves as the secondary winding, and the central solenoid serves as the primary winding. During the occurrence or decay of a magnetic field induced by a current in a solenoid, a toroidal electric field arises,
    ionizing gas and creating a plasma current around the current. The pinch effect due to the missed current makes the charged
    plasma particles tend toward the center of the plasma current. However, the plasma current itself is unstable and some of the plasma touches the holding reservoir, which leads to the cooling of the plasma and impedes any reaction. For these reasons, the tokamak also has a toroidal excitation winding located around the holding reservoir in order to create an extremely strong toroidal magnetic field. The interaction of the toroidal magnetic field with the poloidal magnetic field created by the plasma current leads to a relatively stable plasma confinement.
    In stellar plasma confinement is carried out by means of magnetic fields created by external windings, without relying on the plasma current. In the stellarator, the toroidal excitation winding, like in a tokamak, induces a relatively strong toroidal magnetic field in which plasma is created. In addition to the toroidal magnetic field, a coil field is created by the windings spirally arranged around the toroidal holding tank. The combination of a toroidal field with a spiral magnetic field generates a total twisted magnetic field that ensures the relative stability of the plasma device.
    The difficulty in stellarators is the problem of creating plasma in devices of considerable size and providing the very strong MarHHTrforo field required.
    Closest to the present invention is a method of confining and heating a plasma, including creating a plasma in an axisymmetric chamber, maintaining a pulsed axial current in it, which leads to pinching into a cord extended along the axis of the chamber, and creating an external magnetic field with respect to the plasma. using a system of windings spirally wound on the chamber, while the external magnetic field meets the condition for a change in the stability margin q - reverse between the boundary of the plasma cord and the wall of the chamber.
    This method is implemented in a known device controlled thermo-nuclear synthesis, containing an axisymmetric chamber, means for creating a plasma and maintaining
    217269
     a pulsed axial current and a system of windings to create magnetic fields external to the plasma wound on the chamber.
    5 The known method is to confine the plasma by capturing a toroidal floor in the cord and pointing the toroidal field, which changes its sign when passing from the cord to the wall of the cable to the opposite. The known device contains external windings, which, together with the cord current, create poloidal and toroidal fields, which are close in size, and the toroidal field changes its sign in the outer plasma region.
    All named devices have common features, and all of them should have
    20, the required value of the stability margin q, defined as the average length, traveled in the toroidal direction to a single poloidal angle of rotation of the magnetic field lines on the flow surface, referred to the main radius of the torus:
    . dz / c) 9 q 5-,
    0
    where Z is the distance traveled in the toroidal direction; b - poloidal angle of movement;
    R is the main radius of the torus. The flow surface is defined as a surface on which the magnetic flux density does not have a component normal to it. If r is a small torus radius, then the condition of MHD stability is
    | q | itt; (1) dq / Jr 0. (2)
    Eia
    0
    5 The value of / - -j I must be up to 1 q oG
    large enough to satisfy the Mercier criteria. Tokamak-type devices and those stellarator devices, in which a significant plasma current is observed, basically satisfy condition (1) by working with the whole plasma. In contrast, reverse z-pinch-type devices work when IqU 1
    5 throughout the plasma. Substantially large
    (g dq /
    value / t / implying 14
    a significant width is obtained in a pinch with a reverse field by changing the sign of q to the opposite at the plasma boundary along the radius of the plasma pinch. In the case of a pinch with a reverse field, the flow surfaces are axially symmetric, and q is expressed in terms of the toroidal magnetic field B, the poloidal magnetic field BP, the main radius of the torus R and the small radius of the torus r are quite similar to that of the circular tokamak:
     2L. E
    (3)
    Since BP is directed everywhere in the same way, changing the sign of q can only be obtained by changing the direction B. In a pinch with an inverse field, the condition of inversion of the sign of q can be fulfilled for a short time, since the field configuration is needed to be maintained in a known device only in the presence of poloidal currents in the plasma, which quickly decay, and the magnetic retention of the cord quickly becomes ineffective,
    The purpose of the invention is to increase the plasma temperature by reducing the interaction of the plasma with the wall.
    This goal is achieved in that according to the method of confining and heating the plasma, including creating a plasma in an axisymmetric chamber, maintaining a pulsed axial current in it, leading to plasma pinching in a cord extended along the axis of the chamber, and creating a magnetic field external to the plasma. With the help of a system of windings spirally wound around the chamber, the external magnetic field meets the condition for a change in the stability margin q on the reverse side of the plasma cord boundary to the chamber wall, the external magnetic field is created are of the spiral type by passing the currents through the system of the first and second spiral windings wound in one direction with equal pitch and equally displaced one relative to the other along the chamber axis, while the currents in the first and second windings are opposite in direction, and the values of the currents in the windings and plasma current the cord is selected from the condition within the plasma cord,
    In addition, according to dependent characteristics, the currents in the spiral windings can be equal in magnitude, a longitudinal magnetic field can be imposed, including
    direction with current in the plasma cord. The specified field can be created by changing the ratio of currents in the spiral windings, the magnitude of the spiral and longitudinal magnetic
    fields are chosen so that the separatrix
    the magnetic field is inside
    camera, and its position can
    set by changing the current in the cord.
    To implement the proposed
    In a device comprising an axisymmetric chamber, means for creating a plasma and maintaining a pulsed axial current therein, and a system of windings for creating magnetic fields external to the plasma wound on the camera, the system of windings contains the first and second spiral windings a direction with equal pitch and equally displaced one relative to the other along the axis of the chamber HN, and means for maintaining oppositely directed currents in said windings.
    The device can be equipped with a means of independently maintaining the currents in the first and second spiral windings, which can be two or three. Windings can
    be wound at an angle of 45 to the KajMepbi axis, and the camera itself is made of a toroidal configuration.
    Figure 1 shows a controlled thermo-nuclear synthesis device;
    realistically the proposed method, a general view; Fig. 2 is the same, the section along the main axis Topaj in Fig. 3 is an example of the implementation of spiral-HbSTc windings; figure 4 - device
    view from above; figure 5 - section aa in FIG. 4 | figure 6 presents the dependence of the components of the current density j, j, the magnetic field, BQ and safety margin q from
    dimensionless radius g / Gd; Fig. 7 is a graphical illustration of the surfaces of the magnetic flux on two partial radii of the proposed device; 8 - simplified
    diagram of the device shown in figure 2.
    The device (FIGS. 1 and 2) contains a toroidal chamber 1 containing the corresponding gas at a given low pressure. The first wall 2 of the chamber is made of thin-walled stainless steel, which contributes to the rapid penetration of the toroidal electric field and the occurrence of plasma current. Wall 2 is located inside the toroidal shell 3, made of a relatively thick copper sheet, forming a toroidal cavity 4. The latter is vacuumed through the tubes 5 and the collector 6 by means of a vacuum pump (not shown). The chamber 1 is evacuated through the tubes 7 and the collector 8 with the same vacuum pump.
    Shell 3 (Figs. 4 and 5) has a ceramic bridge 9 serving to interrupt the toroidal conducting trajectory around shell 3. The conductivity of wall 2 is sufficiently small relative to the conductivity of the plasma in order to reduce energy losses. Thus, the magnetic field can penetrate the conductive envelope 3 through the ceramic bridge 9 and penetrate the wall 2, since it is relatively thin and has less conductivity than the material from which the envelope 3 is made. At the same time, the wall 2 creates an electric bridge across the ceramic bridge 9, and a conductive sheath contributes to the stabilization of the plasma.
    As in the case of Tokamak devices, the plasma current is created by a toroidal electric field induced by a solenoid winding 10 located axially with the main axis of the toroidal chamber 1 and inside the torus. A toroidal electric field is created when the solenoid winding 10 and the additional coils 11 introduced to direct the poloidal flow outside the wall 2 are turned on. The solenoid coil 10 and the additional coils 11 are fed in an ordinary way from an energy source (not shown), and the change in electric current in the winding 10 causes change in magnetic flux binding
    night coil formed by wall 2. The change in flow causes the formation of a plasma current in the volume
    J cameras 1.
    A number of the first spiral windings 12 are wound on the frame 13. surrounding the sheath 3. The first windings (FIG. 2) are evenly placed around the small circumference of the frame 13, which can be drawn out of the two halves bolted together. A plurality of second spiral windings 14 are wound on
    5 frame 13 is practically between the corresponding turns of the first windings. Each of the windings 12 and 14 may be formed by a plurality of conductors 15, which may have a rectangular cross section and
    isolated from one another. The conductors 15 may have central channels 16 for circulating refrigerant to cool the conductors.
    5 The first and second windings 12 and 14 appeared spiral, although they do not form real spirals in the sense of winding them on round cylinders. The windings 12 and 14 are wound the same way so that the first windings, after a complete rotation around the torus, are connected to the first windings, and the second windings are connected to the second windings. In this case, continuous windings are formed all the way around the main axis of the torus. The number of turns of the windings must be an integer or an integer + 1/2 turns. In the latter case, one first winding turns into another when it is first walked
    the first winding during the second bypass of the torus. The same is true for the second windings 14.
    The first windings 12 are powered from the DC source 17, and the second windings 14 are powered from the DC source 18. Sources 17 and 18 of direct current have opposite polarity, so that through the corresponding first and second windings the current flows in opposite directions. Such currents provide a helical magnetic field with a steady state in the fuse of chamber 1 summed with a poloidal magnetic flux induced by the plasma current.
    Spiral windings 12 and 14 are preferably wound with such
    five
    0
    five
    in a step that provides relatively small interwind forces and plasma stability is good. An angle of about relative to the minor axis of the torus is most acceptable.
    As shown in FIGS. 1-3, two first windings and two second windings located around a small torus circumference can be wound. Three such windings can also be
    used to more fully fill the chamber with a plasma that is less stable. Under certain conditions, there may be more windings. The power sources can be connected so that the current through the first windings can be equal to or slightly more than the current through the second windings, while the pure toroidal magnetic field is created by the spiral windings 12 and 14. The total current in the second windings 14 is equal to half the current plasma.
    Additional coils 11 may be employed to create a vertical magnetic field in the plasma in order to balance the action of the ring force, to try to expand the plasma over a large radius, or to tune the equilibrium plasma for better stability.
    The device can look holes.
    The device works as follows.
    The plasma current generated when the solenoid winding 10 is turned on and the additional turns 11 reaches a maximum of 40 kA at an amplitude of magnetic flux of about 0.3 Wb with an increase time of about 10 ms. Plasma-to-pressure ratio of 1/3 , 1 while maintaining good stability, the typical plasma temperature T should be about 100 volts at a density of about 10 1 / cm, magnetic flux density of about 1 kG, retention time of about 0.3 ms of energy and pulse duration „„ “For about 30 ms. The total current in the first windings is about 20 kA, and in the second windings it is also about 20 kA. The ratio of the average radius g
    the plasma current to the average radius of the windings rvf is of the order of 0.75. Under such conditions, the qualitatively equilibrium profiles of certain parameters (Fig. 6) are determined, the indicated equilibrium profiles are shown in arbitrary units.
    The links between the various system parameters and their effect on the operation of the system are complex and depend on many factors. The curves in FIG. 6 are obtained on the basis of certain parameters, which were chosen arbitrarily.
    For the curves shown, the aspect ratio, which is the ratio of a large torus radius to a smaller one, is large. More specifically, the parameters shown are as follows: j - density
    current in the direction of the minor axis of the torus; j d - current density in the direction
    around the minor axis; B is the magnetic flux density in the direction of the minor axis; B0 is the stability margin, from that to the B and pitch of the magnetic field lines, as previously defined (1). The parameter g / Gd is the ratio of the coordinate of the small radius to the small radius of the separatrix, and this ratio is estimated at an angle of 45 to the X / Gd axis in Fig. 7, which also shows the C and D surfaces of the magnetic flux generated at these conditions at points A and B in Fig.6. Stability Condition
    is passing q through zero. The analysis of the stability of the plasma in the implementation of the proposed method is difficult, since the description becomes very difficult for certain configurations. To achieve a modified effect, for example, it is desirable to work with a high aspect ratio. In such cases, the toroidal effects can be neglected and limited to a cylindrical approximation. The criterion of MHD stability of Mercier in this case can be in the form of a Saidam criterion:
    1 (1113) 4 2
     g v jr
    Cords can be made stable by profiling B and q. Externally, the plasma portion is stabilized by a high shear and a small relative to the axial field. The inner part of the plasma is stable when there is a pressure distribution in it. In these configurations, the axial field is reversed, i.e. there is a zero point axial field in the plasma. The distribution profile of the parameters must be supported: to maintain stability throughout the entire discharge. it
    represents one of the difficulties of implementing a pinch with a reverse field.
    The physical point of view of the construction of FIGS. 1-5 and the curves of FIGS. 6 and 7, it can be concluded that the twisted magnetic field generated by the plasma current and the spiral magnetic field created by the windings 12 and 14 lead to the creation of surfaces magnetic flux, with the stability margin q has a significant decrease in characteristics and monotonously decreases, changing sign, near the outer boundary of the plasma,
    With equal currents in the spiral windings, B2 is absent, except for plasma induced by poloidal currents. However, the average value of B on the surface of the stream may not be zero, as can be seen from Fig. 8, which is a simplification of Fig. 2. Winding 12 and 14 are represented by single conductors. The dashed lines 19 and 20 divide the space in chamber 1 into quadrants I.- IV. On these lines, the toroidal magnetic field is zero. In quadrants I and III, the toroidal field is created by the first windings 12 and is directed out of the plane shown in Fig. 8. In quadrants P and IV, the toroidal field is directed in the opposite direction. A toroidal field averaged over a circular loop 21 is zero. If the circle is drawn into an ellipse 22, then the toroidal field averaged over the loop is not zero. For loop 22, the trajectories are longer in quadrants I and UI and shorter in quadrants of PI IV. Trajectories are also closer to the first windings 12 in quadrants I and P1, where the toroidal field is stronger, and farther from the second windings 14 in quadrants I and IV in a weakened toroidal field . Both the excess length and the large field create a situation where the gain of the average value makes quadrants I and 111 dominant. This creates a medium toroidal
    the field on the loop 22, directed out of the plane in FIG. Near the plasma center, a purely toroidal field is generated by a poloidal plasma current. At a point near the plasma boundary, the effect of maintaining the poloidal plasma current is relatively much weaker and can be outweighed by the action of the toroidal field. This leads to a change in the sign of q with balanced windings, when the corresponding currents and the field of the corresponding polarity are applied. The proposed device is radically different both in the principle of operation and in design from the known ones, which was shown by examples of tokamaks, stellarators and plasma-cord devices with a reverse field, although the proposed device has common features with each of the listed ones: tokamak, it needs current
    plasma to generate a magnetic flux of the appropriate configuration, and the configuration does not collapse as a result of diffusion of the flow. Toroidal excitation windings rather than spiral windings are required for the camcorder, while the proposed device requires spiral windings rather than toroidal windings. For a tokamak, the condition
    in the proposed device, this is not required. The proposed device requires that q change the sign, and in tokamak this is not accomplished, in a similar way
    the difference of the proposed device from the stellarator.
    The advantage over pinch devices with reverse field is that in known devices
    the mode of operation with the required 1 m profile q can be realized in a short time. The proposed device can provide a quasi-stationary mode of operation and increase
    retention time and plasma temperature.

     77 /// 7 W
    15 12 15 / J / 4. / j 2
    FIG. J
    Phage. 7 HORS Order 1008/63
    Branch PPP Patent, g
    --gog
    ° nd o, s r /
    (afnoSecf / bie profiles
    Hk / t.e
    T2
    FIG. in Circulation 387 Subscription
    gog
    - city street Project 5 4
    权利要求:
    Claims (13)
    [1]
    1. A method of holding and heating the plasma, including creating a plasma in an axisymmetric chamber, maintaining a pulsed axial current in it, leading to lynching of the plasma into a cord extended along the axis of the chamber, and creating a magnetic field external to the plasma using a system of windings spirally wound to the camera, while the external magnetic field meets the condition for changing the sign of the safety margin to the opposite along the radius of the plasma cord, characterized in that, in order to increase the temperature of the plasma by reducing the interaction of the plasma They are provided with a wall and an external magnetic field of a spiral type by passing currents through a system of first and second spiral windings wound in the same direction with equal pitch and equally offset relative to each other along the chamber axis, while the currents in the first and second windings are opposite in direction, and the magnitude of the currents in the windings and the current of the plasma cord select conditions <1 within the plasma cord.
    sz
    Fog 1
    SU ..., 1217269
    [2]
    2. The method according to claim 1, characterized in that the currents in the spiral windings are created equal in magnitude.
    [3]
    3. The method according to p, 1, characterized in that impose an external longitudinal magnetic field,
    [4]
    4. The method according to p. 3, characterized in that the external magnetic field is created coinciding in direction with the current in the plasma cord.
    [5]
    5. The method according to claim 3, with the fact that the longitudinal magnetic field is created by changing the ratio of currents in spiral windings.
    [6]
    6. The method according to claim 1, characterized in that the magnitude of the spiral and longitudinal magnetic fields is chosen so that the magnetic field separatrix occupies a position inside the chamber.
    [7]
    7. The method according to claim 6, characterized in that the current in the cord is changed until the magnetic field separatrix occupies a position inside the chamber.
    [8]
    8. A device for holding and heating a plasma, containing an axisymmetric chamber, means for creating a plasma and maintaining a pulsed axial current in it, and a winding system for creating magnetic fields external to the plasma wound on the chamber, characterized in that the winding system contains first and second spiral windings, wound in the same direction with equal pitch and equally offset relative to one another along the chamber axis, and means have been introduced to maintain oppositely directed currents in said windings.
    ✓ '
    [9]
    9. The device according to claim 1, characterized in that it introduced a means of independently maintaining currents in the first and second spiral windings.
    [10]
    10. The device according to p, 8, characterized in that. that the windings are wound at an angle of 45 with respect to the axis of the chamber.
    [11]
    11. The device according to claim 8, characterized in that it contains two first and two second spiral windings.
    [12]
    12. The device according to claim 8, wherein the device comprises three first and three second spiral windings.
    [13]
    13. The device according to claim 8, characterized in that the camera is made of a toroidal configuration.
    类似技术:
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    US3219534A|1965-11-23|Plasma confinement apparatus employing a helical magnetic field configuration
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    同族专利:
    公开号 | 公开日
    CA1164109A|1984-03-20|
    IT1125945B|1986-05-14|
    AU529873B2|1983-06-23|
    DE2933800A1|1980-08-07|
    FR2447662A1|1980-08-22|
    JPS55102200A|1980-08-05|
    AU5455580A|1980-08-07|
    FR2447662B1|1984-05-11|
    IT7968709D0|1979-08-24|
    CH646830A5|1984-12-14|
    GB2046007A|1980-11-05|
    GB2046007B|1983-06-15|
    US4302284A|1981-11-24|
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    US4638177A|1985-11-14|1987-01-20|Westinghouse Electric Corp.|Rotating flux transformer|
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    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    US06/007,503|US4302284A|1979-01-29|1979-01-29|Helical field stabilization of plasma devices|
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