Compact copper conductor tokamak construction method, equipment and medium

Abstract

The invention discloses a compact copper conductor tokamak construction method, equipment and a medium, and relates to the technical field of index evaluation, and a quantitative evaluation system is constructed by obtaining evaluation indexes of a tokamak device; determining parameter thresholds of evaluation parameters in the quantitative evaluation system based on device operation conditions; determining large radius and small radius thresholds of the compact device based on the parameter thresholds; determining the boundary of the plasma according to the large radius threshold value and the small radius threshold value; a compact device is constructed based on plasma boundaries. By establishing a quantitative index system of Tokamak comprehensive engineering technology capability, the range of core parameters such as large radius and small radius of the plasma can be rapidly determined, the dimension chain can be more accurately determined, conflicts between physical requirements and engineering implementation caused by large errors of the dimension chain are reduced, and the method is suitable for industrial production. And the engineering capability reaches the standard during miniaturization and compact design of the device.

Description

Technical Field

[0001] The invention relates to the technical field of magnetic confinement fusion and data evaluation, and in particular to a method, equipment and medium for constructing a compact copper conductor tokamak. Background Art

[0002] Tokamak is the device type that is closest to building a fusion reactor in the research and development of magnetic confinement fusion energy. According to existing knowledge, to realize the ultimate utilization of fusion energy, it is necessary to improve the fusion triple product of Tokamak. To improve the fusion triple product, the plasma current must be increased. Increasing the plasma current means that the toroidal magnetic field and the scale of the device need to be increased. The increase in the scale of the device means a substantial increase in the construction cost of the device. Therefore, it is necessary to design a compact Tokamak to reduce costs. However, during the development of the compact Tokamak, it is necessary to achieve the quantitative indicators of the engineering and technical capabilities of a large device in a smaller device. For the three major devices that have carried out fusion reaction experiments, their plasma currents are not less than 3MA, the toroidal magnetic field exceeds 3T, and the fusion triple product is close to or exceeds 10 21 m -3 skeV level. TFTR has a large radius (R = 2.6m), a small radius (a = 0.9m), a plasma current (Ip = 3MA), and a toroidal magnetic field (Bt = 6T); JET has a large radius (R = 2.96m), a small radius (a = 1.25m), a plasma current (Ip = 4.8MA), and a toroidal magnetic field (Bt = 3.45T); JT-60U has a large radius (R = 3.3m), a small radius (a = 1.0m), a plasma current (Ip = 5MA), and a toroidal magnetic field (Bt = 4.2T). However, although these three devices have verified the feasibility of tokamaks to achieve fusion reactor construction, the devices are large in scale (large radius 2.6-3.3m, small radius 0.9-1.25m), and the construction cost is high, which is not conducive to improving the economy of fusion energy.

[0003] Therefore, in order to ensure the operation of the compact tokamak, it requires high plasma current and many comprehensive engineering and technical indicators. In order to improve the quantitative indicators of these engineering and technical capabilities, it is necessary to increase the plasma current and small radius, and reduce the toroidal magnetic field and large radius; on the other hand, from the perspective of plasma operation and confinement analysis, increasing the plasma current requires a corresponding increase in the toroidal magnetic field (to maintain a sufficiently large safety factor q), and requires the use of a relatively large large radius and a smaller small radius (in order to layout the ohmic magnets to provide sufficient magnetic flux to generate and maintain a large plasma current); therefore, in terms of improving engineering capabilities and plasma operation, there is a conflict between physical requirements and engineering capabilities; this conflict is particularly prominent in the miniaturization and compact design of the device, which is also one of the key issues that need to be resolved in the development of a compact tokamak. Summary of the invention

[0004] The technical problem to be solved by the present invention is that it is difficult to take into account both physical requirements and engineering capabilities when designing a device in a compact manner, and the engineering capabilities are not up to standard. The purpose is to provide a method, equipment and medium for constructing a compact copper conductor tokamak. By establishing a quantitative indicator system for the comprehensive engineering and technical capabilities of the tokamak, the core parameter ranges such as the large radius and small radius of the plasma can be quickly determined, the dimension chain can be determined more accurately, and the conflict between physical requirements and engineering implementation caused by large errors in the dimension chain can be reduced, so as to achieve engineering capabilities that meet the standards when the device is miniaturized and compactly designed.

[0005] The present invention is achieved through the following technical solutions:

[0006] A first aspect of the present invention provides a method for constructing a compact copper conductor tokamak, characterized by comprising the following specific steps:

[0007] Obtain the evaluation indicators of the tokamak device and build a quantitative evaluation system;

[0008] Determine parameter thresholds of evaluation parameters in the quantitative evaluation system based on the device operating conditions;

[0009] determining large radius and small radius thresholds for the compact device based on the parameter thresholds;

[0010] Determine the boundary of the plasma according to the large radius threshold and the small radius threshold;

[0011] Construction of compact devices based on plasma boundaries.

[0012] Furthermore, the construction of the quantitative evaluation system specifically includes:

[0013] Obtain the comprehensive engineering and technical capability evaluation indicators of tokamaks, and construct a quantitative evaluation system including normalized current, compactness factor and ring diameter ratio.

[0014] Furthermore, in the quantitative evaluation system, the process of determining the normalized current includes: obtaining the plasma current and the large radius and toroidal magnetic field, and constructing a normalized current evaluation index, specifically including:

[0015] I N =Ip / (R*Bt)

[0016] Among them, I N represents the normalized current, Ip represents the plasma current, R represents the major radius, and Bt represents the toroidal magnetic field.

[0017] Furthermore, in the quantitative evaluation system, the process of determining the compact factor includes: obtaining the plasma current and the maximum radius, and constructing a compact factor evaluation index, specifically including:

[0018] F C =Ip / R

[0019] Among them, F C represents the compactness factor, Ip represents the plasma current, and R represents the major radius.

[0020] Furthermore, in the quantitative evaluation system, the process of determining the ring diameter ratio includes: obtaining the plasma current and the major radius, and constructing the ring diameter ratio evaluation index, which specifically includes:

[0021] A=R / a

[0022] Among them, A represents the annular ratio, R represents the large radius, and a represents the small radius.

[0023] Furthermore, the step of determining the large radius and small radius thresholds of the target device specifically includes:

[0024] According to the normalized current evaluation index, the first upper limit of the large radius is determined, including: R1 N / (Ip*Bt);

[0025] According to the compact factor evaluation index, the second upper limit of the large radius is determined, including: R2 <Ip / F C

[0026] Compare the first upper limit and the second upper limit, and take the smaller value as the reference value upper limit of the large radius R;

[0027] According to the evaluation index of the ring-diameter ratio, combined with the upper limit of the reference value of the large radius R, the lower limit of the reference value of the small radius a can be calculated, specifically including: a>R / A;

[0028] Among them, I N represents the normalized current, F C represents the compactness factor, A represents the annular diameter ratio, Ip represents the plasma current, R represents the large radius, Bt represents the toroidal magnetic field, and a represents the small radius.

[0029] Furthermore, the step of determining the boundary of the plasma comprises:

[0030] According to the reference value lower limit of the large radius and the upper limit of the small radius, the left and right boundaries of the plasma are calculated, including:

[0031] Pb_L=Ra

[0032] Pb_R=R+a

[0033] Among them, Pb_L represents the left boundary of plasma, Pb_R represents the right boundary of plasma, R represents the large radius, and a represents the small radius.

[0034] ​Furthermore, the construction of a compact device based on plasma boundaries specifically includes:

[0035] Based on the plasma edge, a dimension chain is obtained, based on which the first wall, the vacuum chamber and the magnet of the compact device are determined.

[0036] A second aspect of the present invention provides an electronic device, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein when the processor executes the program, a method for constructing a compact copper conductor tokamak is implemented.

[0037] A third aspect of the present invention provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements a method for constructing a compact copper conductor tokamak.

[0038] Compared with the prior art, the present invention has the following advantages and beneficial effects:

[0039] By establishing a quantitative indicator system for the comprehensive engineering and technical capabilities of the Tokamak, the core parameter ranges such as the large and small radius of the plasma can be quickly determined, and the dimension chain can be determined more accurately, reducing the conflict between physical requirements and engineering implementation caused by large errors in the dimension chain, and achieving engineering capabilities when miniaturizing and compacting the device;

[0040] In a smaller compact device, it is possible to achieve higher plasma current, fusion triple product, and higher quantitative indicators of comprehensive engineering and technical capabilities that can match those of large tokamaks, and have the ability to carry out core-level fusion parameter operations;

[0041] It can quickly determine the size chain of the device, reduce repeated iterative designs between physical engineering, and improve design efficiency. BRIEF DESCRIPTION OF THE DRAWINGS

[0042] In order to more clearly illustrate the technical solutions of the exemplary embodiments of the present invention, the following briefly introduces the drawings required for use in the embodiments. It should be understood that the following drawings only illustrate certain embodiments of the present invention and should not be regarded as limiting the scope. For those of ordinary skill in the art, other relevant drawings can be obtained based on these drawings without creative work. In the drawings:

[0043] Figure 1 is a flow chart of a construction method in an embodiment of the present invention;

[0044] Figure 2 It is a schematic diagram of the dimension chain of a compact copper conductor Tokamak in an embodiment of the present invention;

[0045] Figure 3It is a schematic diagram of the dimension chain of a compact copper conductor tokamak with an operating plasma current of 3MA (magnetic field of 3T) in an embodiment of the present invention;

[0046] Figure 4 It is a schematic diagram of the structural layout of a compact copper conductor tokamak device in an embodiment of the present invention. DETAILED DESCRIPTION

[0047] In order to make the objectives, technical solutions and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with embodiments and drawings. The exemplary embodiments of the present invention and their description are only used to explain the present invention and are not intended to limit the present invention.

[0048] As a possible implementation, Figure 1 As shown, the first aspect of this embodiment provides a method for constructing a compact copper conductor tokamak, by obtaining the evaluation index of the tokamak device, constructing a quantitative evaluation system; determining the parameter threshold of the evaluation parameter in the quantitative evaluation system based on the device operating conditions; determining the large radius and small radius thresholds of the compact device based on the parameter thresholds; determining the boundary of the plasma according to the large radius threshold and the small radius threshold; constructing the compact device based on the plasma boundary. By establishing a quantitative indicator system for the comprehensive engineering and technical capabilities of the tokamak, not only can the core parameter ranges such as the large radius and small radius of the plasma be quickly determined, but also the dimension chain can be determined more accurately, because the large error of the dimension chain brings about the conflict between physical requirements and engineering implementation, and iterations are reduced; and in combination with the macro process, the overall layout of the main components of the device such as the magnet and vacuum chamber is established.

[0049] In some possible implementations, the comprehensive engineering technology capability evaluation index of the tokamak is obtained, and a quantitative evaluation system including normalized current, compactness factor and ring diameter ratio is constructed. N , refers to the ratio between the plasma current Ip and the large radius R and the toroidal magnetic field Bt. The higher the value, the stronger the device's ability to confine current; the compactness factor, refers to the ratio between the plasma current Ip and the large radius R. The larger the value, the more compact the device; the annular diameter ratio, refers to the ratio between the large radius R and the small radius a. The smaller the value, the more compact the device.

[0050] In the quantitative evaluation system, the process of determining the normalized current includes: obtaining the plasma current and the large radius and toroidal magnetic field, and constructing the normalized current evaluation index, which specifically includes:

[0051] I N =Ip / (R*Bt)

[0052] Among them, I N represents the normalized current, Ip represents the plasma current, R represents the major radius, and Bt represents the toroidal magnetic field.

[0053] The process of determining the compact factor includes: obtaining the plasma current and the maximum radius, and constructing a compact factor evaluation index, which specifically includes:

[0054] F C =Ip / R

[0055] Among them, F C represents the compactness factor, Ip represents the plasma current, and R represents the major radius.

[0056] The process of determining the ring diameter ratio includes: obtaining the plasma current and the maximum radius, and constructing the ring diameter ratio evaluation index, which specifically includes:

[0057] A=R / a

[0058] Among them, A represents the annular ratio, R represents the large radius, and a represents the small radius.

[0059] In some possible implementations, such as Figure 2 As shown in the figure, TF represents a toroidal field magnet, CS represents an ohmic field magnet, PF represents a coil, VV represents a vacuum chamber, FW represents a first wall, PLASMACURRENT Ip (i.e., Ip) represents a plasma current, and I N represents the normalized current, F C represents the compactness factor, A represents the annular diameter ratio, R represents the large radius, Bt represents the toroidal magnetic field, a represents the small radius, Pb_L represents the left side of the plasma boundary, Pb_R represents the right side of the plasma boundary, and Radia represents the radial direction. Figure 2 This is a schematic diagram of the dimension chain of a compact copper conductor Tokamak, which mainly includes the plasma large radius, small radius and the thickness distribution of each component of the device along the radial direction, which is determined as follows:

[0060] By establishing a quantitative index system for the comprehensive engineering and technical capabilities of tokamaks, the dimension chain of compact devices is determined by benchmarking the relevant indicators of large devices; the determined dimension chain refers to the clearly given radial dimensions of the device, which is the data in one-dimensional space, including the dimension data of components such as the plasma large radius, small radius, toroidal field magnet, ohmic field magnet, poloidal field magnet, vacuum chamber, and first wall. According to the three major devices (TFTR, JET, and JT-60U) that have carried out fusion reaction experiments, their plasma currents are not less than 3MA, and the toroidal magnetic field exceeds 3T. Therefore, the core parameters Ip and Bt of the compact copper conductor tokamak are determined to be 3MA and 3T respectively. Under this condition, if the quantitative indicators of the comprehensive engineering and technical capabilities of tokamaks such as normalized current, compact factor, and ring diameter ratio are to be close to or not less than the corresponding indicator values ​​of the three major devices that have carried out fusion experimental research, the parameters of the device such as the large radius R and the small radius a can be inferred.

[0061] like Figure 3 As shown, TF represents a toroidal field magnet, CS represents an ohmic field magnet, PF represents a coil, VV represents a vacuum chamber, FW represents a first wall, Ip represents a plasma current, R represents a large radius, Bt represents a toroidal magnetic field, a represents a small radius, and Radia represents a radial direction. Figure 3 The following is a schematic diagram of the dimension chain of a compact copper conductor tokamak with a running plasma current of 3MA (magnetic field of 3T); the specific steps are as follows:

[0062] (1) To increase the normalized current I N Not less than 0.5, according to I N =Ip / (R*Bt)≥0.5, substituting Ip=3.0MA, Bt=3.0T into the previous formula, we can get the upper limit of the maximum radius R1<2.0m;

[0063] (2) By the compactness factor (F C =Ip / R) is not less than 1.6, according to F C =Ip / R≥1.6, substitute Ip=3.0MA into the previous formula, and we can get another upper limit value of the large radius R2<1.875m; compare R1 and R2, and take the smaller value as the upper limit of the reference value of the large radius R, that is, R<1.875m;

[0064] (3) Since the ring diameter ratio (A=R / a) does not exceed 3, combined with the reference value upper limit of the large radius R of 1.875m, the lower limit of the small radius a can be obtained, that is, a>0.625m.

[0065] In some possible embodiments, since the toroidal magnet straight column section, ohmic magnet, polar magnet, vacuum chamber, first wall and other components need to be densely arranged on the left side of the plasma boundary Pb_L=Ra, that is, in the space on the strong field side of the device; the continued decrease of the large radius R and the increase of the small radius will cause the left side of the plasma boundary Pb_L=Ra to move to the left, reducing the space within the strong field side Ra, and further affecting the spatial arrangement of other components of the device; therefore, the lower limit of the reference value of the large radius R and the upper limit of the small radius a are interrelated, which are related to the overall compactness of the device.

[0066] In some possible implementations, such as Figure 4 The figure shows a schematic diagram of the structural layout of a compact copper conductor Tokamak device, which mainly includes the overall layout of toroidal field magnets, ohmic field magnets, poloidal field magnets, vacuum chamber, first wall and other components in a two-dimensional poloidal plane. The overall layout includes:

[0067] The toroidal field magnet TFC is a D-shaped copper coil. The TF coil can generate a maximum magnetic field of 3T at a large radius R = 1.78m.

[0068] The ohmic field magnet is tightly wound around the straight column section of the toroidal field magnet to increase the radius of the magnet, thereby increasing the magnetic flux and the volt-seconds. The volt-seconds provided can make the 3MA plasma current climb to the plateau.

[0069] The poloidal field magnets (PF1, PF2, PF3, PF4, PF5, PF6, PF7, PF8) are located between the toroidal field magnet TF and the vacuum chamber VV. They are large circular copper conductors with multiple layers and multiple turns of rectangular cross-section. The poloidal field magnets are symmetrical about the midplane. Figure 3 The coils above the midplane are marked in the figure, and there are 8 coils below the midplane; among them, the PF1, PF2, PF3, and PF4 coils are tightly wrapped around the Ohm field magnet, reducing the gap between PF and CS, making full use of the space, and providing space for increasing the small radius. The cross-sectional shape of the PF7 magnet is changed to a diamond shape, which is conducive to making full use of the space between the vacuum chamber VV and the toroidal field magnet TF, making the magnet layout more compact; each magnet is independently powered to improve the flexibility of the configuration (large elongation ratio, high triangle change), thereby increasing the plasma current.

[0070] The vacuum chamber VV is a container for confining plasma. It is located inside the toroidal field coil TF and in the space surrounded by all the poloidal field coils (PF1, PF2, PF3, PF4, PF5, PF6, PF7, and PF8). The vacuum chamber adopts a double-layer thin-wall structure that is connected in an annular direction, which can meet the requirements of extremely high vacuum cleanliness and high structural strength, and has a certain stabilizing effect. The material used is Inconel625 to increase the resistivity of the vacuum chamber and reduce the eddy current in the vacuum chamber. The shape of the vacuum chamber is also approximately the letter "D", which can make full use of the space inside the toroidal magnetic field and increase the volume of the vacuum chamber in order to confine more plasma.

[0071] The first wall FW is located inside the vacuum chamber VV, and is the closest component to the plasma inside the vacuum chamber, playing the role of protecting the vacuum chamber; the first wall has the characteristics of being thin and strong, so as to meet the requirements of less force and space occupation, and ensuring a large space for time-constrained plasma. The first wall compactly matches the cross-sectional shape of the vacuum chamber and the plasma, which is conducive to increasing the plasma volume and running a higher plasma current.

[0072] The divertor Div is located at the bottom of the vacuum chamber VV. Similar to the first wall FW, it is the component closest to the plasma inside the vacuum chamber and plays a role in protecting the vacuum chamber. The divertor is also required to have the ability to handle high heat flow and ion flow control.

[0073] The method described in this embodiment uses a compact copper conductor tokamak, which is more conducive to achieving plasma with large plasma current, large deformation, and large magnetic field. For example, the HL-3 tokamak of the invention has a large normalized current (0.56), a high compact factor (1.7), and a low ring diameter ratio (2.7) under the condition that the device scale is equivalent to that of DIII-D and ASDEX-U, reaching the international leading level, and can obtain higher core parameters related to fusion, such as a high fusion triple product (more than 1×10 20 m - 3 skeV, with impact 10 21 m -3 skeV level capability), greatly improving the overall performance of the device; this method not only makes the tokamak coil layout simple and conducive to engineering implementation, but also has high plasma parameters (Ip=3MA, Bt=3T), and has the ability to carry out core-level plasma research. It has good application prospects in the burning plasma research stage of magnetic confinement fusion.

[0074] A second aspect of this embodiment provides an electronic device, including a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein when the processor executes the program, a method for constructing a compact copper conductor tokamak is implemented.

[0075] A third aspect of this embodiment provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements a method for constructing a compact copper conductor tokamak.

[0076] The specific implementation methods described above further illustrate the objectives, technical solutions and beneficial effects of the present invention in detail. It should be understood that the above description is only a specific implementation method of the present invention and is not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present invention should be included in the scope of protection of the present invention.

Claims

1. A method for constructing a compact copper conductor tokamak, It is characterized in that The specific steps include: Obtain the evaluation indicators of the tokamak device and build a quantitative evaluation system; Determine parameter thresholds of evaluation parameters in the quantitative evaluation system based on the device operating conditions; determining large radius and small radius thresholds for the compact device based on the parameter thresholds; Determine the boundary of the plasma according to the large radius threshold and the small radius threshold; Construction of compact devices based on plasma boundaries.

2. The method for constructing a compact copper conductor Tokamak according to claim 1, It is characterized in that The construction of the quantitative evaluation system specifically includes: Obtain the comprehensive engineering and technical capability evaluation indicators of tokamaks, and construct a quantitative evaluation system including normalized current, compactness factor and ring diameter ratio.

3. The method for constructing a compact copper conductor Tokamak according to claim 2, It is characterized in that In the quantitative evaluation system, the process of determining the normalized current includes: obtaining the plasma current and the large radius and toroidal magnetic field, and constructing a normalized current evaluation index, which specifically includes: I N =Ip / (R*Bt) Among them, I N represents the normalized current, Ip represents the plasma current, R represents the major radius, and Bt represents the toroidal magnetic field.

4. The method for constructing a compact copper conductor Tokamak according to claim 2, It is characterized in that In the quantitative evaluation system, the process of determining the compact factor includes: obtaining the plasma current and the maximum radius, and constructing a compact factor evaluation index, which specifically includes: F C =Ip / R Among them, F C represents the compactness factor, Ip represents the plasma current, and R represents the major radius.

5. The method for constructing a compact copper conductor Tokamak according to claim 2, It is characterized in that In the quantitative evaluation system, the process of determining the ring diameter ratio includes: obtaining the plasma current and the major radius, and constructing the ring diameter ratio evaluation index, which specifically includes: A=R / a Among them, A represents the annular ratio, R represents the large radius, and a represents the small radius.

6. The method for constructing a compact copper conductor Tokamak according to claim 1, It is characterized in that The specific steps of determining the large radius and small radius thresholds of the target device include: According to the normalized current evaluation index, the first upper limit of the large radius is determined, including: R1 N / (Ip*Bt);​ According to the compact factor evaluation index, the second upper limit of the large radius is determined, including: R2 <Ip / F C Compare the first upper limit and the second upper limit, and take the smaller value as the reference value upper limit of the large radius R; According to the evaluation index of the ring-diameter ratio, combined with the upper limit of the reference value of the large radius R, the lower limit of the reference value of the small radius a can be calculated, specifically including: a>R / A; Among them, I N represents the normalized current, F C represents compactness factor, A represents ring diameter ratio, Ip represents plasma current, R represents large radius, Bt represents toroidal magnetic field, and a represents small radius.

7. The method for constructing a compact copper conductor Tokamak according to claim 1, It is characterized in that The step of determining the boundary of the plasma comprises: According to the reference value lower limit of the large radius and the upper limit of the small radius, the left and right boundaries of the plasma are calculated, including: Pb_L=Ra Pb_R=R+a Among them, Pb_L represents the left boundary of plasma, Pb_R represents the right boundary of plasma, R represents the large radius, and a represents the small radius.

8. The method for constructing a compact copper conductor Tokamak according to claim 1, It is characterized in that The construction of a compact device based on plasma boundaries specifically includes: A dimension chain is obtained from the plasma boundary, from which the first wall, the vacuum chamber and the magnet of the compact device are determined.

9. An electronic device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, It is characterized in that When the processor executes the program, the compact copper conductor tokamak construction method according to any one of claims 1 to 8 is implemented.

10. A computer-readable storage medium having a computer program stored thereon, It is characterized in that When the program is executed by a processor, the method for constructing a compact copper conductor Tokamak as claimed in any one of claims 1 to 8 is implemented.

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