KR100886888B1 - Automatic re-centering device of superconducting central solenoid system - Google Patents

Abstract

The present invention relates to an automatic center recovery apparatus for a superconducting CS coil system, and has an object to withstand lateral loads such as earthquake loads and electromagnetic loads, radial displacement loads, and the like. To this end, the present invention is a CS coil structure of the superconducting tokamak device including a recentering device 40 sliding in accordance with the deformation of the preload structure 30 at the lower end of the TF coil structure, the recentering device 40, A housing 43 connected to the lower portion of the preload structure 30; and a disk spring 41 installed inside the housing 43; and one end of the housing 43 penetrating through the housing 43 and the disk spring 41; A center rod 44 restraining the disk spring 41 therein; and a round head bolt 42 connected to one end of the center rod 44 to support the lower portion of the preload structure 30 with respect to the TF coil structure. It is characterized by comprising.

Description

Automatic center recovery of superconducting cs coil system {AUTOMATIC RE-CENTERING DEVICE OF SUPERCONDUCTING CENTRAL SOLENOID SYSTEM}

The present invention is a CS coil structure installed in the inner center of the TF coil structures of the superconducting tokamak device to induce the plasma according to the change of the current value, Cs coil of the superconducting tokamak device to ensure the stability according to thermal, structural, electrical deformation It is about a structure.

The Tokamak device, a fusion experiment device, is a toroidal coil for confining deuterium in a plasma state to a strong magnetic field, a poloidal coil for generating a plasma and controlling its position and shape, and changes the value of electric current to the plasma according to the law of electromagnetic induction. It consists of a central solenoid coil that induces a current. Coil structures for supporting the weight of these large coils and the magnetic force by the strong magnetic field are manufactured according to the characteristics of each coil. Since the assembly error is determined according to the precision of the coil structure, the structure should be manufactured in consideration of the characteristics of the assembly.

Conventional tokamak devices have been difficult to operate for a long time due to Joule heat loss due to high current by using a phase conducting conductor, but recently a design has been made to enable continuous operation using a superconducting conductor having no electrical resistance. Since the phase-conducting tokamak device operates at room temperature, the thermal characteristics of the coil structure were not the main considerations. Also, unlike the superconducting coils, the phase-conducting coils did not significantly reduce the driving ability due to the stress caused by the magnetic force.

1 illustrates a superconducting coil structure of a superconducting tokamak device. As described above, the superconducting coil structure of the tokamak device includes a toroidal coil structure 60, which is made of an in-pipe stranded conductor (CICC) in which a superconducting wire is enclosed by a rectangular metal tube, and then the conductor is connected to the winder equipment. It comprises a coil wound in the form of D, 16 such D-shaped coil is made. The supercritical liquid helium is flowed through the in-pipe twisted conductor at a pressure of about 5 atm, and the superconducting wire is cooled to cryogenic temperature to become a superconducting coil. When a 35 kA direct current flows here, the magnetic field strength reaches a maximum of 7.2 T, and the magnetic field traps the plasma in the tokamak. The toroidal coils continuously form a toroidal magnetic field. The central solenoid (CS) coil and the poloidal coil generate a plasma by rapidly changing the poloidal magnetic field, and control the position and shape of the plasma.

The magnet system of the tokamak device is composed of the toroidal coil, the central solenoid coil and the pololid coil. The central solenoid coil and the structure are at the center of the tokamak device, and the polo coil coil (not shown) and the PF coil structure 100 are three pairs (up to 5, 6, 7 PF coil structures) symmetrically surrounding the outer periphery. There is a vacuum vessel in which the plasma is confined is configured in the donor form in the inner space of the D-shaped TF coil structure.

The superconducting coil of the superconducting tokamak device operates at a cryogenic temperature of about 4.5K and is vulnerable to structural deformation and thermally unstable. Therefore, it is necessary to establish an environment that satisfies the operating conditions in order to improve the stability of the tokamak operation.

The superconducting coil is composed of eight CS coils and six PF coils in a symmetrical structure from the center and operates at cryogenic and high magnetic fields, and thus requires a supporting structure that can protect them structurally, thermally, and electrically. In addition, the support structure is installed through the connecting structure to the TF coil structure which is operated at the same temperature for thermal stability.

The CS coil is located at the center of the tokamak and the design of the main structure has more limited design requirements than any other magnetic structure due to the change of current application rate and the distribution of electromagnetic force caused by the stacking of multiple coils. One of these design requirements is that the coils have different electromagnetic forces according to various operating scenarios.

However, radial electromagnetic forces can cause sliding at the coil interface, and vertical electromagnetic forces can cause separation of the coil interface. In addition, the plasma collapse or incomplete alignment in the coil assembly step may cause the lateral behavior of the coil.

On the other hand, the CS coil structure is required to minimize the effect on the TF coil structure while in contact with the TF coil structure while fluidly responding to the displacement caused by the expansion and contraction of the CS coil structure.

Therefore, the technical problem to be achieved in the present invention is to secure the thermal, structural, and electrical stability of the central solenoid coil of the superconducting tokamak device operating at cryogenic temperature (4.5K) to absorb sufficient strength and shrinkage deformation to withstand electromagnetic forces to absorb superconducting tokamak It is to provide a CSS coil structure of the device.

Recentering device with a built-in disk spring is installed in the lower portion of the preload structure to provide the CS coil structure of the superconducting tokamak device to minimize the impact on the TF coil structure while absorbing the displacement caused by the deformation of the CS coil structure.

In the CS coil structure of the superconducting tokamak device of the present invention for solving the above technical problem, the CS coil structure is installed in the inner center of the TF coil structures of the superconducting tokamak device to induce plasma in accordance with the change of the current value, the The CS coil structure is connected to the inner upper portion of the TF coil structure 60, and the CS coil structure absorbs the transverse displacement with respect to the TF coil structure at a portion connected to the inner upper portion of the TF coil structure 60. It has a flow plate 20, wherein the CS coil structure comprises a recentering device 40 which is slid in the longitudinal direction of the CS coil structure to absorb the longitudinal displacement with respect to the TF coil structure, The disc spring 41 is installed inside the recentering device 40, and the round head bolt 42 is connected to one side of the disc spring 41, so that Is formed in the side extrusion is characterized in that the CS coil structures and coil structures TF maintain a certain gap.

In the CS coil structure is installed in the inner center of the TF coil structures of the superconducting tokamak device to induce the plasma according to the change of the current value, the support lug 10 is integrally coupled to the inner upper portion of the TF coil structure 60; and the A flow plate 20 connected to the lower side of the support lug 10; and a preload structure 30 connected to the other end of the flow plate 20 and positioned inside the TF coil structure; and the lower portion of the preload structure 30. It provides a CS coil structure of the superconducting tokamak device displacement is absorbed, characterized in that it comprises a re-centering device 40 connected to and sliding in accordance with the deformation of the preload structure 30 at the lower end of the TF coil structure.

The recentering device 40 includes: a housing 43 connected to a lower portion of the preload structure 30; and a disk spring 41 installed inside the housing 43; and the housing 43 and a disk spring ( 41, a center rod 44 penetrates the disk spring 41 inside the housing 43 while being penetrated through the 41; and a preload structure 30 for the TF coil structure connected to one end of the center rod 44. It provides a Cs coil structure of the superconducting tokamak device which displacement is absorbed, characterized in that it comprises a round head bolt 42 for supporting the lower part.

Locking nut 45 is fitted to the outer circumference of the center rod 44 protruding out of the housing 43 to limit the range in which the center rod 44 is contracted by the disc spring 41. The present invention provides a CS coil structure of a superconducting tokamak device in which displacement is absorbed.

The superconducting tokamak absorbing displacement is characterized in that the center nut 46 is screwed to the opposite end of the round head bolt 42 in the center rod 44 to couple the center rod 44 to the housing 43. Provides a COS coil structure of the device.

A fixing key groove 47 is formed at one inner side of the housing 43, and a fixing key 48 is formed at an outer side of the center rod 44 to rotate the locking nut 45 or the center nut 46. Provided is a COS coil structure of a superconducting tokamak device in which displacement is absorbed, wherein the city center rod 44 is prevented from being lost.

The insulation plate 49 is positioned at the lower end of the preload structure 30, the horizontal member 56 of the welding plate is positioned at the lower portion of the insulation plate, and the insulation plate does not allow electricity to flow between the preload structure and the TF coil structure. It is to provide a CS coil structure of the superconducting tokamak device which displacement is absorbed.

The housing 40 is connected to the lower portion of the preload structure 30 by the horizontal member 56 of the welding plate, and the preload structure and the welding plate are screwed by the stud bolt 53 and the hex nut 53a. The flat bar 54 is connected between the hex nuts to provide the CS coil structure of the displacement-absorbing superconducting tokamak device, characterized in that supporting the hex nuts to each other.

The end of the round head bolt 42 is screwed to one side of the center rod, the non-screwed portion of the round head bolt is supported horizontally by the flat bar 55, the flat bar 55 is positioned horizontally And one end of which is attached to one side of the center rod and the other end of which is attached to the head side of the round head bolt, thereby providing the CS coil structure of the displacement-absorbing superconducting tokamak device.

The locking plate 52 is attached to the housing 43 under the center nut 46, thereby providing a Cs coil structure of the superconducting tokamak device in which displacement is absorbed.

As described above, in the CS coil structure of the superconducting tokamak device in which the displacement of the present invention is absorbed, a support lug connected to the TF coil structure is connected to the preload structure by a fluid plate, and supports the TF coil structure under the preload structure. By installing the recentering device, the thermal, structural and electrical stability of the central solenoid coil of the superconducting tokamak device operating at cryogenic temperatures can be provided to absorb sufficient strength and shrinkage deformation to withstand electromagnetic forces. .

Since the recentering device with the disc spring installed is installed under the preload structure, it can minimize the influence on the TF coil structure while absorbing the displacement caused by the deformation of the CS coil structure.

Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings.

2 is a cross-sectional view of the CS coil structure according to the present invention.

As shown in FIG. 2, the CS coil structure of the superconducting tokamak device according to the present invention induces plasma in accordance with the change of the current value, structurally and thermally protecting each coil from electromagnetic and thermal loads during operation, and It is made to withstand lateral loads such as loads and electromagnetic loads, radial displacement loads, and the like.

The CS coil structure of the superconducting tokamak device is classified into three types according to its function: preload structure, TF connection structure, and coil lead support structure.

The preload structure must withstand the working load directly adjacent to the coil and the TF connection structure bolts or centers with the TF coil structure at the top / bottom. The lead support structure is for supporting the coil lead.

The TF connection structure of the present invention is composed of a support lug 10, a flow plate 20 and a recentering device 40 as a lower connection structure.

The support lug 10 is composed of eight elements on a plane for electrical insulation of the TF coil structure, and is bolted when assembled. The support lug 10 is bolted to the top of the TF coil structure to support the vertical electromagnetic load.

The flow plate 20 has a radially flexible structure to absorb not only the weight of the coil and the structures but also the displacement difference between the CS and the TF coil structures during cooling and operation. The flow plate 20 is bolted to the support lug 10 and the upper block 33 of the preload structure.

The recentering device 40 should have no vertical fixed point in order to allow vertical deformation during cooling and operation. The recentering device 40 may have a transverse load that may occur depending on the earthquake load, plasma collapse, electromagnetic force of the coil leads, and alignment of each coil. Even the system is designed to be always in place.

The preload structure 30 is connected to the other end of the flow plate 20 and is located inside the TF coil structure 60. The preload structure 30 is fixedly connected to the TF coil structure by the support lug 10 and the flow plate 20.

The preload structure 30 is formed with the outer shell 31 on the outside and the inner shell 32 on the inside. Preload structure 30 is the upper block 33 is formed on the upper side and the lower block 34 is formed on the lower side. The flow plate 20 is connected to the upper side of the upper block, the recentering device 40 is connected to the lower side of the lower block.

Figure 3 shows an enlarged cross-sectional state of the recentering device 40 of the CS coil structure according to the present invention.

As shown in FIG. 3, the recentering device 40 is connected to the lower portion of the preload structure 30 and slides according to the deformation of the preload structure 30 at the lower end of the TF coil structure.

The recentering device 40 is provided with an elastic support member contacting the inner side of the toroidal coil 60 with elastic force, and the CS coil structure and the TF coil structure maintain a constant gap by the elastic support member. The elastic support member includes, for example, a disk spring 41 and a round head bolt 42.

The main function of the recentering device is to always keep the CS coil structure in the center direction and to limit excessive lateral movement from external loads. The loads acting on the CS coil structure include seismic loads, lateral loads due to plasma collapse, and displacement due to thermal contraction differences with the TF coil structure. Therefore, a design considering such a load is necessary.

The horizontal seismic load is as follows.

North-South: 0.2 g, East-West: 0.4 g, where g is the gravitational acceleration (= 9.81 m / sec ² ).

The lateral force due to the earthquake is calculated by the following equation and the result is about 0.112 MN.

The maximum lateral electromagnetic load acting on the CS coil is about 0.25 MN when the plasma is radially drifted. Since the transverse electromagnetic loads are to be supported at the upper and lower portions of the CS coil structure, the design load acting on the recentering device is 0.125 MN, which is half of the calculated electromagnetic load.

When looking at the displacement after cooling of the CS coil structure, the position where it is connected to the TF structure is about 2.43 mm, and the CS coil is about 1 ~ 1.5 mm, and about 1.5 ~ at the round head bolt end of the recentering device. Central deformation of about 2 mm occurs.

In the case of the TF coil structure, a displacement of about 1.73 mm occurs at the cooling center in the vertical center position and 2.3 mm when the TF coil is applied. This is because the in-plane electromagnetic force causes the largest deformation at the center position. On the other hand, the upper and lower parts (connection of the CS coil structure) have a displacement of about 2.2 mm for both CD and TF on.

As described above, it is determined that the displacement difference between the CS coil structure and the TF coil structure is about 1 mm at the position where the recentering device is assembled, and the displacement will be absorbed by the disc spring 41 of the recentering device. Because of this the axial force of the center rod 44 will be increased.

4a and 4b show the load distribution acting on the recentering device. The maximum load of the recentering device can be calculated for the following two cases.

Case 1 (FIG. 4A)

Case (2) (FIG. 4B)

Referring to the configuration of the present invention in more detail, the recentering device 40 is the housing 43, the disk spring 41, the center rod 44, the round head bolt 42, the locking nut 45 and the center nut Including 46.

The housing 43 is connected to the lower portion of the preload structure 30. In the present invention, one side of the housing 43 is fastened to the lower portion of the preload structure 30 by bolting.

Upper and lower portions of the housing 43 are attached with welding plates formed of vertical horizontal members, respectively, and serve as a connecting member for connecting the housing to other members. The welding plates 56 and 57 are attached to the upper part of the housing, and the other welding plates 58 and 59 are attached to the lower shelf of the housing. Vertical members 57 and 58 of the welding plate are vertically positioned above and below the housing. The horizontal members 56 and 59 of the welding plate are respectively connected to both sides of the vertical member, and a plurality of holes penetrate through the middle of the horizontal member to be bolted to the other member.

The insulating plate 49 is positioned at the lower end of the preload structure 30, and the horizontal member 56 of the welding plate is positioned below the insulating plate. Holes of the same size pass through the insulating plate at the same position as the holes penetrated through the horizontal members. The insulating plate prevents electrical conduction between the preload structure and the TF coil structure.

A bush 51 is mounted in the hole of the horizontal member 56 and the insulating plate 49, and a stud bolt 53 is inserted in the bush to bolt-couple the horizontal member and the preload structure. A hex nut 53a is coupled to an end of the stud bolt, and a flat bar 54 is connected between the hex nuts to support the hex nuts.

Inside one side of the housing 43 is a hollow as large as the size of the disk spring 41 is formed through. On one side of the hollow of the housing 43, a boundary portion 43a for constraining the disk spring 41 is formed to protrude inward. In the center of the boundary portion 43a, a hollow having a size through which the center rod 44 can penetrate is formed.

In the housing 43 of the present invention, the boundary portion 43a is formed in the hollow middle of the housing 43, and the disk springs 41 are installed at both sides of the boundary portion 43a. The disk spring 41 is formed in a washer shape, as shown in Figure 5, folds to one side at a predetermined angle in the hollow portion of the washer in the cross section. This shape is a shape in which the hollow inner side of the disk spring 41 protrudes more than the outer side in cross section. 5 is an enlarged cross-sectional view of the disk spring 41 of the recentering device 40 according to the present invention.

Inconel 718 is used as the material for the disc spring. Inconel 718 is a very strong, nonmagnetic, widely used material at high and low temperatures. The outer and inner diameters are 80 mm and 41 mm, respectively, and the thickness is 5 mm. The maximum amount of deformation is 1.7 mm, and the maximum weight during deformation is at least 4500 kgf. The numerical presentation of the present invention is only an example, and the numerical value is not limited.

The disc spring 41 has a resilient force by itself by varying the folded direction when the disc spring 41 is installed in the housing 43. One or more disk springs 41 are installed in the same direction in which the hollow inner side projects, and then one or more disk springs 41 are installed in the opposite direction of the hollow inner direction. In this way, an appropriate number of disc springs 41 are housed inside the housing 43.

The center rod 44 penetrates the housing 43 and the disk spring 41, and one end of the center rod 44 restrains the disk spring 41 inside the housing 43. One end of the center rod 44 is formed to have a size penetrating the hollow of the disk spring 41 and the boundary 43a. The other end of the center rod 44 is formed to have a size penetrating the hollow except for the hollow of the boundary portion 43a in the housing 43. The other end of the center rod 44 penetrates through the housing 43 and protrudes out of the housing 43. A portion of both ends of the center rod 44 is formed with a screw line. A plurality of disc springs 41 are interposed between the boundary portion 43a and the center rod 44 formed in the hollow size of the housing 43.

The round head bolt 42 is connected to one end of the center rod 44 to support the lower portion of the preload structure 30 against the TF coil structure. The round head bolt is rounded in the head portion and is supported by the TF coil structure horizontally as shown in FIG. 3, and is slidable vertically.

The end of the round head bolt 42 is screwed to one side of the center rod, the portion of the round head bolt that is not screwed is supported horizontally by the flat bar (55). The flat bar 55 is horizontally positioned in FIG. 3 so that one end is attached to one side of the center rod and the other end is attached to the head side of the round head bolt.

A locking nut 45 is fitted to the outer circumference of the center rod 44 protruding out of the housing 43 to limit a range in which the center rod 44 is contracted by the disc spring 41. The locking nut 45 consists of two nuts with opposite directions of the internal threads. The locking nut 45 is formed by two nuts having opposite directions of the screw thread, and is locked to the center rod 44 so that the locking nut 45 is fixed without change in the fastening position.

The center nut 46 is screwed to the opposite end of the round head bolt 42 in the center rod 44 to couple the center rod 44 to the housing 43. The center nut 46 also serves to bind the disc spring 41 in the left side (on FIG. 3) of the boundary portion 43a to the center rod 44. The locking plate 52 is attached to the housing 43 under the center nut 46 after the tightening of the center nut to prevent the center nut from loosening due to vibration.

A fixing key groove 47 is formed in the hollow one side of the housing 43, and a fixing key 48 protrudes from the outer side of the center rod 44. The fixing key 48 is located in the fixing key groove 47 to prevent the center rod 44 from turning when the locking nut 45 or the center nut 46 is rotated. FIG. 7 is a side view of the fixing key 48 of the recentering device 40 as seen from AA of FIG. 6B, in which the fixing key 48 is formed only on the upper side of the center rod 44 so that the center rod 44 itself rotates. Prevent it.

When the internal structure of the housing 43 is collectively put together, a plurality of disk springs 41 are provided on both sides of the inner boundary portion 43a of the housing 43 in different directions in the hollow projection direction. The center rod 44 penetrates through the hollow of the disc spring 41, and the disc spring 41 is positioned so that the end of the center rod 44 having a relatively large outer circumference is located outside the preload structure 30. The center rod 44 penetrates into the hollow. A round head bolt 42 is installed at an outer portion of the preload structure 30 of the center rod 44 to support the preload structure 30 in the TF coil structure. The locking nut 45 is coupled to the outer side of the preload structure 30 of the center rod 44, and the center nut 46 is coupled to the inner side of the preload structure 30 of the center rod 44.

Looking at the arrangement example and the assembling procedure of the disk spring 41, four left springs (disk A) of FIG. 3 are arranged in series, and eight right springs (disk B) of FIG. .

At this time, the protrusions of the disk springs are arranged in the same direction by three springs in the right spring, and the three disk spring groups of eight groups are arranged to reverse the protrusions of the disk springs. In this case, the projecting portions of the three disk springs are opposed to each other, and the outer ends are opposed to each other. If three disk spring groups are eight groups, eight d intervals as shown in FIG.

In the center nut 46 of the center rod, a double nut is used to limit the displacement, and a fixing key 48 is designed to prevent rotation when the center nut is tightened.

The assembly of the centering device is performed in the following order.

24 springs (disk B) are stacked on the center rod and inserted into the housing from right to left. Here, the fixing key is assembled in advance and fits into the fixing key groove when inserted. After stacking Disk A (4 pieces) and flat washers (41a), tighten the center nut. Then tighten the center nut with a torque wrench. The torque is measured in several stages and the displacement is measured at the right end of the center rod.

Disk A and Disk B form a balance of forces and can be expressed as

,

는 디스크스프링의 그룹(disk A, disk B)에 작용하는 하중이고

는 한 개의 스프링이 최대로 변형되었을 경우, 즉 최대변위(

)일 경우의 하중 값을 나타낸다. 또한 A는 스프링의 단위 배열 수이며 N은 단위배열의 반복수이다. 실제 조립에 사용된 변수를 적용하였을 경우, 두 그룹의 변형 관계는 아래와 같이 표현될 수 있다.here,

,

Is the load acting on the group of disk springs (disk A, disk B)

Is the maximum displacement of one spring, i.e.

) Indicates the load value. Where A is the number of unit arrays in the spring and N is the number of iterations of the unit array. When the variables used in the actual assembly are applied, the deformation relations of the two groups can be expressed as follows.

가 0.5

로 적용된다면 각 그룹의 변형량 및 작용 하중은 아래와 같이 계산될 수 있다.if

0.5

If applied as, the deformation amount and working load of each group can be calculated as follows.

The method of measuring the axial force of the center rod can be calculated using a load cell or by theoretical calculation. In the assembly of the recentering device, the axial force was calculated based on the theoretical calculation method because of the ease of operation. Install a dial gauge at the end of the housing and the center rod and measure the displacement according to the torque change. In the assembly of the recentering device, the torque was applied until the total deformation amount was 8 mm based on the following calculation procedure and result, and the maximum torque was about 150 kgf m.

First, when the total amount of deformation is 8 mm, the deformation of disk B is about 7.1 mm as shown in the following equation, and the axial force acting on disk B is about 7 tons as shown in the following equation.

According to the assembly procedure, after the CS coil structure is seated on the TF coil structure, the recentering device must be finally preloaded. These preloads are applied in the following order.

When assembling CS, round head bolts should be tightened as far as possible to avoid assembly interference. After the assembly, the round head bolt is then brought into contact with the inner diameter (R726 mm) of the TF coil structure.

In the initial design, there was a process of applying the preload after contacting the round head bolt to the TF coil structure. That is, the center nut is rotated in the opposite direction to the preload (counterclockwise direction). However, since the round head bolt is already in contact with the TF coil structure, disk B will have little deformation, and in the case of disk A, the amount of deformation of 0.9 mm will decrease and the axial force of disk A will decrease. In addition, an additional preload is applied after cooling due to the displacement difference caused by the contraction between the TF coil structure and the CS coil structure. Therefore, the preloading step in the assembly at room temperature becomes unnecessary.

As described above, the additional displacement applied to the recentering device with cooling was estimated to be up to 1 mm. When this displacement is added, the total strain is 9 mm, and the amount of deformation and axial force in Disk B are calculated according to the following equations. In conclusion, the axial force acting on each recentering device during operation will be around 8 tons and will support up to 5.3 tons of lateral load (electromagnetic load due to earthquake or plasma collapse).

Looking at the action of the CS coil structure of the superconducting tokamak device according to the present invention made as described above are as follows.

Looking at the assembly action of the recentering device 40 briefly, the center rod 44 is the disk spring with the housing 43 is bolted to the preload structure 30 and the disk spring 41 is in the housing 43. It is penetrated by 41.

The center nut 46 is screwed to the opposite end of the round head bolt 42 in the center rod 44. The center nut 46 is doublely coupled so as not to loosen to couple the center rod 44 to the housing 43.

The locking nut 45 is screwed to the outer circumference of the center rod 44 protruding through the housing 43. The locking nut 45 is doubled so as not to loosen to limit the range in which the center rod 44 is contracted by the disc spring 41.

A fixing key groove 47 is formed at one inner side of the housing 43, and a fixing key 48 is protruded at an outer side of the center rod 44 to rotate the locking nut 45 or the center nut 46. The center rod 44 is prevented from vanishing.

When the preload structure 30 of the CS coil structure of the superconducting tokamak apparatus according to the present invention is horizontally deformed, the flow plate 20 flows in the upper portion of the preload structure 30 to absorb the displacement accordingly. The loads acting horizontally are lateral loads such as earthquake loads and electromagnetic loads, radial displacement loads, and the like.

When the preload structure 30 is horizontally deformed, the lower portion of the preload structure 30 absorbs the displacement due to the elastic force of the plurality of disk springs 41. When the disk spring 41 is contracted, the contraction range is limited by the locking nut 45, and the contraction range or more by the locking nut 45 is not contracted. This is to maintain a constant gap between the CS coil structure and the TF coil structure.

6a and 6b show a state before and after the operation of the disk spring 41 of the recentering device 40 according to the present invention. When the preload structure 30 is horizontally compressed, the main body of the recentering device 40 and the locking nut 45 are separated by a predetermined interval (g), and the disk springs 41 are contracted by the predetermined interval (g).

When the preload structure 30 is vertically deformed, the flow plate 20 flows in the upper portion of the preload structure 30 to absorb the displacement accordingly.

When the preload structure 30 is vertically deformed, the round head bolt 42 of the recentering device 40 slides according to the displacement at the lower portion of the preload structure 30. The round head bolt 42 is connected to the disk spring 41 and slides with elasticity by the disk spring 41.

When the preload structure 30 is deformed in an oblique direction, the vertical deformation process and the horizontal deformation process of the preload structure 30 as described above are combined to form a disk of the fluid plate 20 and the recentering device 40. The spring 41 and the round head bolt 42 work together.

While the invention has been described and illustrated in connection with a preferred embodiment for illustrating the principles of the invention, the invention is not limited to the construction and operation as shown and described. Rather, those skilled in the art will appreciate that many modifications and variations of the present invention are possible without departing from the spirit and scope of the appended claims. Accordingly, all such suitable changes and modifications and equivalents should be considered to be within the scope of the present invention.

1 is a perspective view of a superconducting tokamak device is installed CS coil structure according to the present invention.

Figure 2 is a cross-sectional view of the CS coil structure according to the present invention.

Figure 3 is an enlarged cross-sectional view of the recentering device of the CS coil structure according to the present invention.

4a and 4b is a load distribution state acting on the recentering device according to the present invention.

Figure 5 is an enlarged cross-sectional view of the disk spring of the recentering device according to the present invention.

6a and 6b is a state diagram before and after the operation of the disk spring of the recentering device according to the present invention.

Figure 7 is a side view of the fixing key of the recentering device according to the present invention.

Explanation of symbols on the main parts of the drawings

10. Support Lug 20. Flow Plate

30. Preload structure 40. Recentering device

Claims (10)

In the CS coil structure is installed in the inner center of the TF coil structures of the superconducting tokamak device to induce the plasma in accordance with the change of the current value, The CS coil structure is connected to the inner upper portion of the TF coil structure 60, On the inner upper part and the connecting portion of the TF coil structure 60, the CS coil structure is provided with a flow plate 20 for absorbing the transverse displacement with respect to the TF coil structure, The CS coil structure includes a recentering device 40 sliding in the longitudinal direction of the CS coil structure to absorb the longitudinal displacement with respect to the TF coil structure, The disc spring 41 is installed inside the recentering device 40 and the round head bolt 42 is connected to one side of the disc spring 41 while protruding to one side of the recentering device 40 to form a CS coil structure. CS coil structure of the superconducting tokamak device is displacement is absorbed, characterized in that the TF coil structure maintains a constant gap. In the CS coil structure is installed in the inner center of the TF coil structures of the superconducting tokamak device to induce the plasma in accordance with the change of the current value, A support lug 10 integrally coupled to the inner upper portion of the TF coil structure 60; A flow plate 20 connected to the lower side of the support lug 10; A preload structure 30 connected to the other end of the flow plate 20 and positioned inside the TF coil structure; And The superconducting tokamak device is absorbed displacement characterized in that it comprises a recentering device 40 is connected to the lower portion of the preload structure 30 and sliding in accordance with the deformation of the preload structure 30 at the lower end of the TF coil structure CSS coil structure. The method according to claim 2, The recentering device 40 is A housing 43 connected to the lower portion of the preload structure 30; A disk spring 41 installed inside the housing 43; A center rod 44 penetrating through the housing 43 and the disk spring 41 to constrain the disk spring 41 inside the housing 43; And Cs coil of the superconducting tokamak device which displacement is absorbed, comprising a round head bolt 42 connected to one end of the center rod 44 and supporting the lower portion of the preload structure 30 with respect to the TF coil structure. structure. The method according to claim 3, The locking nut 45 is fitted to the outer circumference of the center rod 44 protruding out of the housing 43, thereby limiting a range in which the center rod 44 is contracted by the disc spring 41. The COS coil structure of the superconducting tokamak apparatus in which the displacement to be made is absorbed. The method according to claim 3, The superconducting tokamak absorbing displacement is characterized in that the center nut 46 is screwed to the opposite end of the round head bolt 42 in the center rod 44 to couple the center rod 44 to the housing 43. Coil structure of the device. The method according to claim 4 or 5, A fixing key groove 47 is formed at one inner side of the housing 43, and a fixing key 48 is formed at an outer side of the center rod 44 to rotate the locking nut 45 or the center nut 46. Cs coil structure of the superconducting tokamak apparatus is absorbed displacement, characterized in that the city center rod (44) is prevented from falling. The method according to claim 3, The insulation plate 49 is positioned at the lower end of the preload structure 30, the horizontal member 56 of the welding plate is positioned at the lower portion of the insulation plate, and the insulation plate does not allow electricity to flow between the preload structure and the TF coil structure. A CS coil structure of a superconducting tokamak device, wherein the displacement is absorbed. The method according to claim 3, The housing 40 is connected to the lower portion of the preload structure 30 by the horizontal member 56 of the welding plate, and the preload structure and the welding plate are screwed by the stud bolt 53 and the hex nut 53a. CS coil structure of the superconducting tokamak apparatus is displacement is absorbed, characterized in that the flat bar 54 is connected between the hex nuts to support the hex nuts. The method according to claim 3, The end of the round head bolt 42 is screwed to one side of the center rod, the non-screwed portion of the round head bolt is supported horizontally by the flat bar 55, the flat bar 55 is positioned horizontally And one end of which is attached to one side of the center rod and the other end of which is attached to the head side portion of the round head bolt. The method according to claim 5, Locking plate 52 is attached to the housing 43 of the lower portion of the center nut 46 to prevent the loosening of the center nut, the displacement of the super-conducting Tosca membrane structure of the superconducting tokamak device.

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