A construction method, device and medium for a compact copper-conductor tokamak

Abstract

The present invention discloses a method, device and medium for constructing a compact copper conductor tokamak, which relates to the technical field of index evaluation. By obtaining the evaluation indexes of the tokamak device, a quantitative evaluation system is constructed; based on the device operation conditions, the parameter thresholds of the evaluation parameters in the quantitative evaluation system are determined; based on the parameter thresholds, the major radius and minor radius thresholds of the compact device are determined; according to the major radius threshold and minor radius threshold, the boundary of the plasma is determined; and based on the plasma boundary, the compact device is constructed. By establishing a quantitative index system for the comprehensive engineering technology capabilities of the tokamak, the ranges of core parameters such as the major radius and minor radius of the plasma can be quickly determined, the dimension chain can be determined more accurately, the conflict between physical requirements and engineering implementation caused by large dimension chain errors can be reduced, and the engineering capabilities can meet the standards when the device is miniaturized and compactly designed.

Description

Technical Field

[0001] The present invention relates to the technical fields of magnetic confinement fusion and data evaluation, and particularly relates to a method, device and medium for constructing a compact copper conductor tokamak. Background Art

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

[0003] Therefore, to ensure the operation of a compact Tokomak, the required plasma current and many comprehensive engineering technical indicators are high. To improve these quantitative indicators of engineering technical capabilities, it is necessary to increase the plasma current and the minor radius, and reduce the toroidal magnetic field and the major radius; on the other hand, from the analysis of plasma operation and confinement, increasing the plasma current requires a corresponding increase in the toroidal magnetic field (to maintain a sufficiently large safety factor q), and it is necessary to use a relatively large major radius and a relatively small minor radius (so as to layout the ohmic magnet to provide sufficient magnetic flux to generate and maintain a large plasma current); thus, in terms of improving engineering capabilities and plasma operation, that is, a conflict is formed 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 problems to be solved in the development of a compact Tokomak. Summary of the Invention

[0004] The technical problem to be solved by the present invention is that it is difficult to balance the physical requirements and engineering capabilities during the miniaturization and compact design of the device, and the engineering capabilities do not meet the standards. The purpose is to provide a method, device and medium for constructing a compact copper conductor tokamak. By establishing a quantitative index system for the comprehensive engineering technology capabilities of the tokamak, it is possible to quickly determine the core parameter ranges such as the major radius and minor radius of the plasma, more accurately determine the dimensional chain, reduce the conflict between physical requirements and engineering implementation caused by large dimensional chain errors, and achieve the compliance of engineering capabilities during the miniaturization and compact design of the device.

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

[0006] In the first aspect of the present invention, a method for constructing a compact copper conductor tokamak is provided, which is characterized by including the following specific steps:

[0007] Obtain the evaluation indexes of the tokamak device and construct a quantitative evaluation system;

[0008] Based on the device operation conditions, determine the parameter thresholds of the evaluation parameters in the quantitative evaluation system;

[0009] Based on the parameter thresholds, determine the major radius and minor radius thresholds of the compact device;

[0010] According to the major radius threshold and minor radius threshold, determine the boundary of the plasma;

[0011] Based on the plasma boundary, construct the compact device.

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

[0013] Obtain the evaluation indexes of the comprehensive engineering technology capabilities of the tokamak and construct a quantitative evaluation system including the normalized current, compactness factor and aspect ratio.

[0014] Furthermore, in the quantitative evaluation system, the determination process of the normalized current includes: obtain the plasma current, major radius and toroidal magnetic field, and construct a normalized current evaluation index, which specifically includes:

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

[0016] where 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 determination process of the compactness factor includes: obtain the plasma current and major radius, and construct a compactness factor evaluation index, which specifically includes:

[0018] F C = Ip / R

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

[0020] Furthermore, in the quantitative evaluation system, the determination process of the aspect ratio includes: obtaining the plasma current and the major radius, and constructing an aspect ratio evaluation index, specifically including:

[0021] A = R / a

[0022] Among them, A represents the aspect ratio, R represents the major radius, and a represents the minor radius.

[0023] Furthermore, the specific steps for determining the thresholds of the major radius and the minor radius of the target device include:

[0024] According to the normalized current evaluation index, determine the first upper limit of the major radius, specifically including: R1 < I N / (Ip * Bt);

[0025] According to the elongation factor evaluation index, determine the second upper limit of the major radius, specifically including: R2 < Ip / F C

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

[0027] According to the aspect ratio evaluation index, combined with the upper limit of the reference value of the major radius R, the lower limit of the reference value of the minor radius a can be deduced, specifically including: a > R / A;

[0028] Among them, I N represents the normalized current, F C represents the elongation factor, A represents the aspect ratio, Ip represents the plasma current, R represents the major radius, Bt represents the toroidal magnetic field, and a represents the minor radius.

[0029] Furthermore, the specific steps for determining the boundary of the plasma include:

[0030] According to the upper limit of the reference value of the major radius and the lower limit of the reference value of the minor radius, calculate the left and right boundaries of the plasma, specifically including:

[0031] Pb_L = R - a

[0032] Pb_R = R + a

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

[0034] Further, the construction of the compact device based on the plasma boundary specifically includes:

[0035] Obtain a dimension chain based on the plasma edge, and determine the first wall, vacuum chamber, and magnet of the compact device according to the dimension chain.

[0036] The second aspect of the present invention provides an electronic device, including a memory, a processor, and a computer program stored on the memory and executable on the processor. When the processor executes the program, it implements a method for constructing a compact copper conductor tokamak.

[0037] The third aspect of the present invention provides a computer-readable storage medium, on which a computer program is stored. When the program is executed by a processor, it 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 index system for the comprehensive engineering technology capabilities of the tokamak, the ranges of core parameters such as the major radius and minor radius of the plasma can be quickly determined, the dimension chain can be determined more precisely, the conflict between physical requirements and engineering implementation caused by large dimension chain errors can be reduced, and the engineering capabilities can meet the standards when the device is miniaturized and compactly designed;

[0040] In a compact device with a relatively small scale, a relatively high plasma current, triple product of fusion, and quantitative index of comprehensive engineering technology capabilities that can match large tokamak devices can be achieved, and the ability to carry out core-level fusion parameter operations is available;

[0041] The dimension chain of the device can be quickly determined, the repeated iterative design between physics and engineering can be reduced, and the design efficiency can be improved. Description of the Drawings

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

[0043] Figure 1 It is the flowchart of the construction method in the embodiments of the present invention;

[0044] Figure 2 It is the schematic diagram of the dimension chain of the compact copper conductor tokamak in the embodiments of the present invention;

[0045] Figure 3Schematic diagram of the dimensional chain of a compact copper conductor tokamak with a plasma current of 3 MA (magnetic field of 3 T) in the embodiments of the present invention;

[0046] Figure 4 Schematic diagram of the structural layout of a compact copper conductor tokamak device in the embodiments of the present invention. Detailed implementation manners

[0047] To make the objectives, technical solutions and advantages of the present invention clearer and more understandable, the present invention will be further described in detail below in combination with embodiments and drawings. The illustrative embodiments of the present invention and their descriptions are only used to explain the present invention and shall not be construed as a limitation to the present invention.

[0048] As a possible implementation manner, as Figure 1 shown, in the first aspect of this embodiment, a method for constructing a compact copper conductor tokamak is provided. By obtaining the evaluation indexes of the tokamak device, a quantitative evaluation system is constructed; based on the device operation conditions, the parameter thresholds of the evaluation parameters in the quantitative evaluation system are determined; based on the parameter thresholds, the major radius and minor radius thresholds of the compact device are determined; according to the major radius threshold and minor radius threshold, the boundary of the plasma is determined; and based on the plasma boundary, the compact device is constructed. By establishing a quantitative index system for the comprehensive engineering and technical capabilities of the tokamak, not only can the core parameter ranges such as the major radius and minor radius of the plasma be quickly determined, but also the dimensional chain can be determined more accurately, reducing the conflicts between physical requirements and engineering implementation caused by large dimensional chain errors, and reducing iterations; and combined with the macroscopic process, the overall layout of the main components such as the device magnet and vacuum chamber is established.

[0049] In some possible implementation manners, the evaluation indexes of the comprehensive engineering and technical capabilities of the tokamak are obtained, and a quantitative evaluation system including the normalized current, compactness factor, and aspect ratio is constructed. Among them, the normalized current I N , refers to the ratio between the plasma current Ip, the major radius R, and the toroidal magnetic field Bt. The higher the value, the stronger the current confinement ability of the device; the compactness factor refers to the ratio between the plasma current Ip and the major radius R. The larger the value, the more compact the device; the aspect ratio refers to the ratio between the major radius R and the minor radius a. The smaller the value, the more compact the device.

[0050] In the quantitative evaluation system, the determination process of the normalized current includes: obtaining the plasma current, major radius, and toroidal magnetic field, and constructing a normalized current evaluation index, specifically including:

[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 determination process of the compactness factor includes: obtaining the plasma current and the major radius, and constructing an evaluation index for the compactness factor, specifically including:

[0054] F C = Ip / R

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

[0056] The determination process of the aspect ratio includes: obtaining the plasma current and the major radius, and constructing an evaluation index for the aspect ratio, specifically including:

[0057] A = R / a

[0058] Wherein, A represents the aspect ratio, R represents the major radius, and a represents the minor radius.

[0059] In some possible implementation manners, as Figure 2 shown, in the figure, TF represents the toroidal field magnet, CS represents the ohmic field magnet, PF represents the coil, VV represents the vacuum vessel, FW represents the first wall, PLASMA CURRENT Ip (i.e., Ip) represents the plasma current, I N represents the normalized current, F C represents the compactness factor, A represents the aspect ratio, R represents the major radius, Bt represents the toroidal magnetic field, a represents the minor 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 It is a schematic diagram of the dimensional chain of a compact copper conductor tokamak, mainly including the plasma major radius, minor radius, and the thickness distribution of each component of the device along the radial direction, and is determined as follows:

[0060] By establishing a quantitative index system for the comprehensive engineering and technical capabilities of the tokamak, and benchmarking the relevant indicators of large devices to determine the dimensional chain of the compact device; the determination of the dimensional chain refers to clearly giving the dimensions of the device in the radial direction, which are one-dimensional space data, including the dimensions of components such as the plasma major radius, minor radius, toroidal field magnet, ohmic field magnet, poloidal field magnet, vacuum vessel, and first wall. According to the three major devices (TFTR, JET, JT - 60U) that have carried out fusion reaction experiments, their plasma currents are not less than 3 MA, and their toroidal magnetic fields exceed 3 T. Therefore, the core parameters Ip and Bt of the compact copper conductor tokamak are determined to be 3 MA and 3 T respectively. Under this condition, if the quantitative indicators of the comprehensive engineering and technical capabilities of the tokamak, such as the normalized current, compactness factor, and aspect 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, then the parameters such as the major radius R and minor radius a of the device can be deduced.

[0061] As shown Figure 3 in the figure, in the figure, TF represents the toroidal field magnet, CS represents the ohmic field magnet, PF represents the coil, VV represents the vacuum vessel, FW represents the first wall, Ip represents the plasma current, R represents the major radius, Bt represents the toroidal magnetic field, a represents the minor radius, Radia represents the radial direction, Figure 3 It is a schematic diagram of the dimensional chain of a compact copper conductor tokamak with an operating plasma current of 3 MA (magnetic field 3 T); the specific steps are as follows:

[0062] (1) If the normalized current I N is not less than 0.5, according to I N = Ip / (R * Bt) ≥ 0.5, substituting Ip = 3.0 MA and Bt = 3.0 T into the above formula, the upper limit value of the major radius R1 < 2.0 m can be obtained;

[0063] (2) From the compactness factor (F C = Ip / R) not less than 1.6, according to F C = Ip / R ≥ 1.6, substituting Ip = 3.0 MA into the above formula, another upper limit value of the major radius R2 < 1.875 m can be obtained; comparing R1 and R2, the smaller value is taken as the upper limit of the reference value of the major radius R, that is, R < 1.875 m;

[0064] (3) From the aspect ratio (A = R / a) not exceeding 3, combined with the upper limit of the reference value of the major radius R of 1.875 m, the lower limit of the minor radius a can be obtained, that is, a > 0.625 m.

[0065] In some possible implementation manners, since on the left side of the plasma boundary Pb_L = R - a, that is, in the space on the strong field side of the device, components such as the straight section of the toroidal magnet, the ohmic magnet, the poloidal magnet, the vacuum vessel, and the first wall need to be densely arranged; further reduction of the major radius R and increase of the minor radius will both shift the left side of the plasma boundary Pb_L = R - a to the left, reducing the space within R - a on the strong field side, and thus affecting the space arrangement of other components of the device; therefore, the lower limit of the reference value of the major radius R and the upper limit of the minor radius a are interrelated and related to the overall compactness of the device.

[0066] In some possible implementation manners, as Figure 4 shown is a schematic diagram of the structural layout of a compact copper conductor tokamak device, mainly including the overall layout of components such as the toroidal field magnet, the ohmic field magnet, the poloidal field magnet, the vacuum vessel, and the first wall in the two-dimensional poloidal plane. In the overall layout, it includes:

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

[0068] The Ohmic field magnet is tightly wound around the straight section of the toroidal field magnet to increase the magnet radius, thereby increasing the magnetic flux, improving the volt-seconds, and providing volt-seconds that can ramp up the plasma current of 3 MA to the flat top.

[0069] The poloidal field magnets (PF1, PF2, PF3, PF4, PF5, PF6, PF7, PF8) are located between the toroidal field magnet TF and the vacuum vessel VV. They are large circular copper conductors with a multi-layer and multi-turn rectangular cross-section. The poloidal field magnets are symmetric about the mid-plane. The coils above the mid-plane have been marked in Figure 3 and there are also 8 coils below the mid-plane. Among them, the PF1, PF2, PF3, and PF4 coils are tightly sleeved around the Ohmic field magnet, reducing the gap between PF and CS, making full use of the space, and providing space for increasing the minor radius. The cross-section shape of the PF7 magnet becomes diamond-shaped, which is conducive to making full use of the space between the vacuum vessel VV and the toroidal field magnet TF, making the magnet layout more compact. Each magnet is independently powered, improving the flexibility of the configuration (large elongation ratio, high triangularity), and thus increasing the plasma current.

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

[0071] The first wall FW is located inside the vacuum vessel VV. It is the component inside the vacuum vessel closest to the plasma and plays a role in protecting the vacuum vessel. The first wall has characteristics such as being thin and light, and having high strength to meet the requirements of less force and less space occupation, and ensuring a large space for time-confining the plasma. The first wall is tightly matched with the cross-section shapes of the vacuum vessel and the plasma, which is beneficial to increasing the plasma volume and operating at a higher plasma current.

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

[0073] The method described in this embodiment uses a compact copper conductor tokamak, which is more conducive to achieving a plasma with a large plasma current, large deformation, and large magnetic field. For example, when the HL-3 tokamak of this invention is used under the condition that the device scale is comparable to that of DIII-D and ASDEX-U, its normalized current is large (0.56), the compactness factor is high (1.7), and the aspect ratio is low (2.7), reaching the international leading level. Higher fusion-related core parameters can be obtained, such as a high fusion triple product (exceeding 1×10 20 m - 3 skeV, with the ability to impact the 10 21 m -3 skeV magnitude), greatly improving the overall performance of the device. This method not only simplifies the coil layout of the tokamak and is conducive to engineering implementation, but also has relatively high plasma parameters (Ip = 3MA, Bt = 3T), and has the ability to conduct core-level plasma research. It has good application prospects in the research stage of burning plasmas in magnetic confinement fusion.

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

[0075] In the third aspect of this embodiment, a computer-readable storage medium is provided, on which a computer program is stored. When the program is executed by a processor, a method for constructing a compact copper conductor tokamak is implemented.

[0076] The specific embodiments described above further elaborate on the purpose, technical solutions, and beneficial effects of the present invention. It should be understood that the above are only specific embodiments of the present invention and are not used to limit the protection scope of the present invention. Any modifications, equivalent replacements, improvements, etc. made within the spirit and principle of the present invention shall be included in the protection scope of the present invention.

Claims

1. A construction method of a compact copper conductor tokamak, characterized in that, It includes the following specific steps: Obtain the evaluation indexes of the tokamak device and construct a quantitative evaluation system; The construction of the quantitative evaluation system includes: Obtain the plasma current, major radius, and toroidal magnetic field, and construct a normalized current evaluation index. The calculation formula includes: I N = Ip / (R * Bt); Obtain the plasma current and major radius, and construct an evaluation index for the compactness factor. The calculation formula includes: F C = Ip / R; Obtain the plasma current and the major radius, and construct an aspect ratio evaluation index. The calculation formula includes: A = R / a; Among them, I N represents the normalized current, F C represents the compactness factor, A represents the aspect ratio, Ip represents the plasma current, R represents the major radius, Bt represents the toroidal magnetic field, and a represents the minor radius; Determine the parameter thresholds of the evaluation parameters in the quantitative evaluation system based on the device operating conditions; Determine the major radius and minor radius thresholds of the compact device based on the parameter thresholds. The specific steps include: Determine the first upper limit of the major radius according to the normalized current evaluation index, specifically including: R1 < I N / (Ip * Bt); Determine the second upper limit of the large radius according to the compactness factor evaluation index, specifically including: R2 < Ip / F C ; Compare the first upper limit and the second upper limit, and take the smaller value as the upper limit of the reference value of the major radius R; According to the aspect ratio evaluation index and in combination with the upper limit of the reference value of the major radius R, the lower limit of the reference value of the minor radius a can be deduced. Specifically, it includes: a > R / A; Determine the boundary of the plasma according to the major radius threshold and the minor radius threshold. The specific steps include: Calculate the left and right boundaries of the plasma according to the upper limit of the reference value of the major radius and the lower limit of the reference value of the minor radius. Specifically, it includes: Pb_L = R - a Pb_R = R + a Among them, Pb_L represents the left boundary of the plasma, Pb_R represents the right boundary of the plasma, the value of R is the upper limit of the reference value of the major radius, and the value of a is the lower limit of the reference value of the minor radius; Construct a compact device based on the plasma boundary.

2. The construction method of the compact copper conductor tokamak according to claim 1, characterized in that, The construction of the compact device based on the plasma boundary specifically includes: Obtain a dimension chain according to the plasma boundary, and determine the first wall, vacuum chamber and magnet of the compact device according to the dimension chain.

3. An electronic device, comprising a memory, a processor, and a computer program stored on the memory and executable on the processor, characterized in that, When the processor executes the program, it implements the method for constructing a compact copper conductor tokamak according to any one of claims 1 to 2.

4. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the program is executed by the processor, it implements the method for constructing a compact copper conductor tokamak according to any one of claims 1 to 2.

Images