A peeling filter suitable for compact fusion reactor and a method for constructing a configuration

Abstract

The application discloses a gourd type divertor suitable for a compact fusion reactor and a configuration construction method, and belongs to the technical field of magnetic confinement nuclear fusion. The divertor adopts a gourd type configuration, wherein the inner and outer divertor legs are designed in an arc shape, and are accompanied by the characteristics of magnetic surface compression at the middle positions of the inner and outer divertor legs and magnetic surface expansion at the bottom positions of the inner and outer divertor legs. The length of the divertor leg is increased, the radiation divertor and the magnetic surface expansion configuration are fully utilized to relieve the thermal load, the influence on the main plasma is greatly avoided, and the particle exclusion and impurity shielding capacity are relatively strong. That is, the length of the divertor leg is increased, the magnetic flux is expanded to reduce the target plate thermal load, the neutron irradiation problem of the fusion reactor divertor, the particle exclusion and impurity shielding function are comprehensively considered, the comprehensive performance is better, and the fusion reactor application prospect is better.

Description

Technical Field

[0001] This invention belongs to the field of magnetic confinement nuclear fusion technology, specifically relating to a gourd-shaped divertor and its configuration construction method suitable for compact fusion reactors. Background Technology

[0002] In recent years, international research on magnetically confined controlled nuclear fusion has made significant progress. Among these, the tokamak boasts the highest overall parameters and is the closest device type to establishing a fusion reactor. Three large-scale tokamak devices internationally—TFTR in the United States, JET in Europe, and JT-60U in Japan—have achieved breakthroughs in magnetically confined nuclear fusion experiments, reaching plasma temperatures of 440 million degrees Celsius, pulsed fusion output power exceeding 16 MW, and an equivalent fusion power gain Q exceeding 1.25. JET set a world record of 59 MJ fusion energy output in 2021. These breakthroughs experimentally validate the scientific feasibility of achieving fusion via the tokamak pathway, indicating that the tokamak is the most likely route to first achieve fusion reactor construction. Currently, fusion research has moved from the principle exploration stage to the exploration stage of the scientific and technological issues of fusion reactors, with some countries beginning to explore the environmental, engineering, and technological aspects of fusion reactors. The International Thermonuclear Experimental Reactor (ITER), the world's largest and most influential international collaborative project, aims to achieve a fusion power gain Q greater than 10 for 400 seconds and a fusion power gain Q greater than 5 for 3000 seconds, verifying the scientific and engineering feasibility of fusion reactors. Currently, ITER has begun mainframe installation and will be operational in a few years, marking the entry of nuclear fusion research into the experimental reactor phase.

[0003] As a core component of a tokamak device, the divertor plays a crucial role in heat and ash removal. The conventional divertor configuration currently used in ITER, with its single-zero design, places heat loads on the inner and outer target plates far exceeding the engineering limit of 10 MW / m² allowed by existing target plate designs, posing a significant challenge to the ITER divertor. Furthermore, future fusion reactors, which require steady-state operation, will face even higher heat loads than ITER. Therefore, it is urgent to explore technologies to reduce the target plate heat load. Currently, the following technologies are being explored and researched to reduce the target plate heat load:

[0004] (1) By designing and changing the structure of the target plate, such as the tilt angle and the target plate material, this technology has been used since the advent of divertors. However, due to the influence of spatial location, engineering development, and material properties, it cannot meet the rapidly increasing demand of divertors to withstand heat loads.

[0005] (2) By increasing the radiation in the divertor region, the thermal power reaching the target plate is reduced, thereby reducing the thermal load on the target plate; this technology may also cause the divertor to operate in a non-target state, which can also alleviate the thermal load on the divertor. This technology mainly relies on injecting impurities into the divertor region, but the introduction of impurities may cause a decrease in the core plasma parameters and reduce fusion performance;

[0006] (3) By optimizing the divertor configuration and increasing the wetted area of ​​the target plate, the requirement for peak heat load on the target plate can be reduced. Target plate wetted area (S = 2πR) t λ q f exp The effective heat-bearing area of ​​the target plate is mainly related to the large radius (R) at the point of impact of the target plate. t ), radial energy decay length (λ) q ), the broadening factor of the magnetic flux at the point of impact relative to the mid-plane (f) exp The radial energy decay length is closely related to the strength of the poloidal magnetic field on the outer mid-plane, and its variation range is relatively small for fixed plasma parameters. The broadening factor is closely related to the magnetic topology at the impact point and the target plate tilt angle. Therefore, the broadening factor can be increased by designing the impact point to a location with a large radius, or by optimizing the configuration or adjusting the target plate tilt angle, thereby increasing the wetted area.

[0007] For configuration optimization techniques, various advanced divertor configurations have been developed, including X-divertors, super X-divertors, and snowflake divertors. X-divertors generate an additional X-point (i.e., a second X-point) by adding one or two pairs of poloidal field coils near the target plate. However, the relatively close distance between the two coils limits the ability to infinitely increase the wetted area of ​​the target plate and control its location. Furthermore, the proximity of the coils to the target plate restricts space for divertor design, posing significant challenges. This is particularly true for divertor configurations in superconducting tokamas, where space constraints prevent the full utilization of the second X-point to alleviate heat flux to the target plate. Therefore, although X-divertors aim to increase the heat flux distribution width and reduce the heat flux amplitude through flow expansion, they still face many challenges and limitations in practical applications. The super X-divertor configuration, by increasing the radial position of the target plate, further increases the wetted area of ​​the target plate and the length of the divertor legs (i.e., the length from the first X point to the target plate), maximizing the divertor's heat dissipation capacity. This configuration not only reduces the radiation load on the core, enabling the core plasma to operate at high power density, but also helps to isolate the connection between the divertor and the core plasma, especially the influence of neutral and impurity particles flowing towards the core region along magnetic field lines. However, the realization of the super X-divertor configuration places extremely high demands on engineering design, especially in the coil design of superconducting tokamak devices. Secondly, designing both the inner and outer divertors with the super X-divertor configuration limits space. If only one of the inner or outer divertors adopts the super X-divertor configuration, the other side will experience a higher thermal load compared to a conventional divertor. By transforming the first-order X-point of the standard divertor into a second-order X-point, which in turn transforms the four branches of the standard X-point into six branches, a snowflake divertor configuration is formed. This configuration creates a very large, extremely low poloidal field region near the X-point, enabling magnetic surface expansion, increasing the wetted area of ​​the plasma, and extending the connection length from the outermost plane to the divertor target plate. The weak field region also enhances particle loss in the vicinity of the X-point. When the plasma passes through a high poloidal specific pressure region where the poloidal magnetic field is close to zero, strong convection diffusion occurs, and then the plasma flows along the four legs towards the target plate, ultimately reducing the thermal load on the target plate. However, the target plate of the snowflake divertor is too close to the main plasma region. Although it can reduce the thermal load, the particle temperature reaching the target plate is very high and the particles are dispersed, making it impossible to effectively control the particles, especially the density of impurity particles.

[0008] Furthermore, in fusion reactors, the function of the divertor is not only heat removal but also particle removal and impurity shielding. Current common divertor target designs directly face high-temperature plasmas exceeding hundreds of millions of degrees Celsius, requiring them to withstand extremely high thermal loads and high-energy fusion neutron irradiation. This places the divertor in a very harsh environment, imposing extremely high demands on the thermal fatigue resistance and neutron irradiation resistance of the divertor target material, and severely impacting the divertor's operational lifespan. Additionally, from a cost and economic perspective, compact fusion reactor designs offer significant advantages, necessitating a relatively compact divertor with a limited size. Summary of the Invention

[0009] To address the challenges of existing technologies for mitigating the thermal load on divertor targets in future fusion reactor applications, such as difficulty in simultaneously achieving divertor particle removal, impurity shielding, high-performance operation of the main plasma, and neglecting neutron irradiation of the divertor, this invention provides a gourd-shaped divertor and its configuration construction method suitable for compact fusion reactors. This invention employs a gourd-shaped divertor configuration that introduces arc-shaped inner and outer divertor legs. The magnetic surface is compressed at the middle of the divertor legs and widened at the bottom. By increasing the length of the divertor legs and expanding the magnetic flux, the thermal load on the target plate is reduced, while simultaneously avoiding impact on the main plasma, resulting in strong particle removal and impurity shielding capabilities.

[0010] This invention is achieved through the following technical solution:

[0011] A gourd-shaped divertor suitable for compact fusion reactors, wherein the configuration of the gourd-shaped divertor includes a main plasma region, a divertor region, and an X-point; the main plasma region is the region where the fusion reaction occurs, which is enclosed by the outermost closed magnetic surface; the X-point is the boundary between the main plasma region and the divertor region; and the divertor region consists of an inner divertor leg and an outer divertor leg.

[0012] Both the inner and outer divertor legs are outwardly convex arc-shaped. The magnetic surface at the middle position of the inner and outer divertor legs is contracted, while the magnetic surface at the bottom position of the inner and outer divertor legs is widened. A divertor target plate is arranged at the bottom position of the inner and outer divertor legs.

[0013] Existing technologies for mitigating the thermal load on divertor targets, when applied to future fusion reactors, face challenges. Firstly, the power flowing into the fusion reactor divertor is 1-2 orders of magnitude higher than in existing divertors, making it difficult to effectively address the thermal load issue. Secondly, existing technologies struggle to simultaneously address divertor particle removal, impurity shielding, high-performance operation of the main plasma, and the problem of neutron irradiation faced by the divertor. The divertor proposed in this invention employs a gourd-shaped configuration, with both inner and outer divertor legs featuring an arc design. This design incorporates magnetic surface compression at the midpoint of the inner and outer divertor legs and magnetic surface expansion at the bottom. This not only increases the length of the divertor legs, fully leveraging the thermal load mitigation effect of the radiative divertor and magnetic surface expansion configuration, but also significantly minimizes the impact on the main plasma, resulting in strong particle removal and impurity shielding capabilities. In other words, this invention reduces the target plate's thermal load by increasing the length of the divertor legs and expanding the magnetic flux, while comprehensively considering the neutron irradiation problem of the fusion reactor divertor, as well as particle removal and impurity shielding functions. It has better overall performance and good prospects for fusion reactor applications.

[0014] In a preferred embodiment, half the distance between the left and right boundaries of the main plasma region of the present invention is equal to the small radius of the plasma.

[0015] In a preferred embodiment, the length of the inner divertor leg or the outer divertor leg of the present invention is equal to 2 to 3 times the small radius of the plasma.

[0016] Secondly, the present invention proposes a configuration construction method for the above-mentioned gourd-shaped divertor, the configuration construction method comprising:

[0017] Arrange the positions of the poloidal field coils;

[0018] By combining the magnitude of the plasma current, a corresponding current combination is applied to the poloidal field coil to obtain the gourd-shaped divertor configuration.

[0019] In a preferred embodiment, the poloidal field coil of the present invention includes a central solenoid coil, a divertor coil, and a shaping field coil;

[0020] The central solenoid coil and the shaping field coil are used to constrain the shape of the main plasma region and maintain the evolution of the plasma region;

[0021] The divertor coil includes an inner divertor coil located between the inner divertor leg and the outer divertor leg, and an outer divertor coil located outside the vacuum chamber, for forming the configuration of the divertor region.

[0022] In a preferred embodiment, the arrangement of the poloidal field coils of the present invention should satisfy the following:

[0023] The center point of the pole section of the internal divertor coil is located to the left of the vertical line passing through point X, and the distance between the center point of the pole section of the internal divertor coil and the vertical line is less than 0.25 times the width of the pole section of the internal divertor coil.

[0024] In a preferred embodiment, the position of the center point of the poloidal section of the internal divertor coil in the vertical direction can be adjusted according to the vertical height requirements of the neutron shielding module. At the same time, the center point of the poloidal section of the internal divertor coil is located near the horizontal line passing through the point of maximum curvature of the divertor leg, and the upper and lower offset distances are less than 1.0 times the height of the poloidal section of the internal divertor coil.

[0025] In a preferred embodiment, the center point of the pole section of the internal divertor coil of the present invention is on the same horizontal line as the point of maximum curvature of the divertor leg.

[0026] In a preferred embodiment, the center point of the pole section of the coil corresponding to the middle position of the divertor leg in the central solenoid coil of the present invention is located near the horizontal line passing through the center point of the pole section of the inner divertor coil, and the upper and lower offset distance is less than 0.5 times the height of the pole section of the inner divertor coil.

[0027] In a preferred embodiment, the center point of the polar section of the coil corresponding to the middle position of the divertor leg in the central solenoid coil of the present invention is on the same horizontal line as the center point of the polar section of the internal divertor coil.

[0028] In a preferred embodiment, the center point of the pole section of the coil corresponding to the bottom position of the divertor leg in the central solenoid coil of the present invention is located near the horizontal line passing through the impact point, and the upper and lower offset distances are less than a threshold.

[0029] In a preferred embodiment, the center point of the polar section of the coil corresponding to the bottom position of the divertor leg in the central solenoid coil of the present invention is on the same horizontal line as the striking point.

[0030] In a preferred embodiment, the center point of the pole section of the external divertor coil of the present invention should be located to the left of the straight line passing through the center point of the pole section of the internal divertor coil and the X point, and the horizontal distance between the center point of the pole section of the external divertor coil closest to the straight line and the straight line is less than 1.0 times the width of the pole section of the coil.

[0031] Thirdly, the present invention proposes a configuration construction system for the above-mentioned gourd-shaped divertor, the configuration construction system comprising:

[0032] A coil layout unit, wherein the coil layout unit arranges the positions of the poloidal field coils;

[0033] In addition, a current loading unit, which, in combination with the magnitude of the plasma current, loads a corresponding combination of currents onto the poloidal field coil to obtain a gourd-shaped divertor configuration.

[0034] Fourthly, the present invention provides an electronic device including a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to implement the steps of the method described in the present invention.

[0035] Fifthly, the present invention provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the steps of the method described in the present invention.

[0036] Compared with the prior art, the present invention has the following advantages and beneficial effects:

[0037] 1. This invention reduces the thermal load on the target plate by using a long-legged divertor and magnetic flux expansion. The bending design of the inner and outer divertor legs increases the length of the divertor legs, which can significantly alleviate the thermal load and greatly avoid the impact on the main plasma. It has a strong particle rejection and impurity shielding capability. In addition, due to the bending of the divertor legs, the divertor target plate can be arranged below the divertor shielding module, which can make the divertor design more compact and also avoid direct bombardment by neutrons as much as possible.

[0038] 2. The gourd-shaped divertor configuration of this invention not only addresses the stronger thermal load problem faced by fusion reactors, but also allows the divertor in the fusion reactor environment to avoid the dual impact of extremely high thermal load and high-energy fusion neutron irradiation, enabling it to focus solely on handling the high thermal load problem and simplifying complex issues. Furthermore, the gourd-shaped divertor configuration allows the divertor target plate to be arranged below the divertor shielding module, resulting in a more compact divertor structure, facilitating neutron shielding and improving tritium breeding rate. It exhibits good overall performance and has promising application prospects in compact fusion reactors. Attached Figure Description

[0039] The accompanying drawings, which are included to provide a further understanding of embodiments of the invention and form part of this application, do not constitute a limitation thereof. In the drawings:

[0040] Figure 1 This is a schematic diagram of the configuration structure of the divertor according to an embodiment of the present invention.

[0041] Figure 2 This is a schematic diagram of the target plate and neutron shielding module of the divertor according to an embodiment of the present invention.

[0042] Figure 3This is a flowchart of the configuration construction method of the divertor according to an embodiment of the present invention.

[0043] Figure 4 This is a schematic diagram of the configuration of the divertor and the layout of the poloidal field coils in an embodiment of the present invention.

[0044] Figure 5 This is a block diagram illustrating the configuration construction system of the divertor according to an embodiment of the present invention.

[0045] Figure reference numerals and corresponding component names:

[0046] 1-Main plasma region, 2-Inner divertor leg, 3-Outer divertor leg, 4-X point, 5-First coil, 6-Second coil, 7-Third coil, 8-Fourth coil, 9-Fifth coil, 10-Sixth coil, 11-Seventh coil, 12-Eighth coil, 13-Ninth coil, 14-Tenth coil, 15-Eleventh coil, 16-Twelfth coil, 17-Thirteenth coil, 18-Fourteenth coil, 19-Fifteenth coil, 20-Sixteenth coil, 21-Inner target plate of divertor, 22-Outer target plate of divertor, 23-Divertor shielding module, 24-Strong field side shielding module, 25-Weak field side shielding module, 26, 27, 28-Neutron linear transport channel, 29-Local area of ​​vacuum chamber. Detailed Implementation

[0047] In the following, the terms “comprising” or “may include” as used in various embodiments of the invention indicate the presence of an inventive function, operation, or element, and do not limit the addition of one or more functions, operations, or elements. Furthermore, as used in various embodiments of the invention, the terms “comprising,” “having,” and their cognates are intended only to indicate a specific feature, number, step, operation, element, component, or combination of the foregoing, and should not be construed as primarily excluding the presence of one or more other features, numbers, steps, operations, elements, components, or combinations of the foregoing, or adding one or more combinations of the foregoing.

[0048] In various embodiments of the invention, the expression "or" or "at least one of A and / or B" includes any combination or all combinations of the words listed simultaneously. For example, the expression "A or B" or "at least one of A and / or B" may include A, may include B, or may include both A and B.

[0049] The expressions used in the various embodiments of the present invention (such as "first," "second," etc.) may modify various constituent elements in the various embodiments, but do not limit the corresponding constituent elements. For example, the above expressions do not limit the order and / or importance of the elements. The above expressions are only used for the purpose of distinguishing one element from other elements. For example, a first user device and a second user device refer to different user devices, although both are user devices. For example, a first element may be referred to as a second element without departing from the scope of the various embodiments of the present invention, and similarly, a second element may also be referred to as a first element.

[0050] It should be noted that if a description is made of "connecting" one component to another, then the first component can be directly connected to the second component, and a third component can be "connected" between the first and second components. Conversely, when a component is "directly connected" to another component, it can be understood that there is no third component between the first and second components.

[0051] The terminology used in the various embodiments of the invention is for the purpose of describing particular embodiments only and is not intended to limit the various embodiments of the invention. As used herein, the singular form is intended to include the plural form as well, unless the context clearly indicates otherwise. Unless otherwise defined, all terms used herein (including technical and scientific terms) have the same meaning as commonly understood by one of ordinary skill in the art to which the various embodiments of the invention pertain. The terms (such as those defined in a generally used dictionary) are to be interpreted as having the same meaning as in the context of the relevant technical field and are not to be interpreted as having an idealized or overly formal meaning, unless clearly defined in the various embodiments of the invention.

[0052] To make the objectives, technical solutions, and advantages of the present invention clearer, the present invention will be further described in detail below with reference to the embodiments and accompanying drawings. The illustrative embodiments and descriptions of the present invention are only used to explain the present invention and are not intended to limit the present invention.

[0053] Example:

[0054] Existing technologies for mitigating the thermal load on divertor targets have many limitations for future fusion reactor applications, making it difficult to effectively solve the thermal load problem. Furthermore, existing technologies struggle to simultaneously address divertor particle removal, impurity shielding, high-performance operation of the main plasma, and do not consider issues such as neutron irradiation faced by the divertor. To address these issues, this embodiment proposes a gourd-shaped divertor suitable for compact fusion reactors. The proposed divertor adopts a gourd-shaped configuration, with both inner and outer divertor legs featuring an arc design. The magnetic surface is compressed at the middle of the divertor legs and expanded at the bottom. By increasing the length of the divertor legs and expanding the magnetic flux, the thermal load on the target plate is reduced, while simultaneously minimizing the impact on the main plasma, resulting in strong particle removal and impurity shielding capabilities.

[0055] The gourd-shaped divertor proposed in this embodiment adopts the following configuration: Figure 1 As shown, the configuration of the divertor includes a main plasma region 1, a divertor region (inner divertor leg 2 and outer divertor leg 3), and point X 4; wherein, the main plasma region 1 is the main region where the fusion reaction occurs, which is surrounded by the outermost closed magnetic surface; point X 4 is the boundary point between the main plasma region 1 and the divertor region; the divertor region consists of two parts: inner divertor leg 2 and outer divertor leg 3.

[0056] The inner divertor leg 2 is an arc shape that bulges to the left (similar to a left bracket), which can increase the length of the leg. The magnetic surface of the inner divertor leg 2 is contracted at the middle position (similar to the knee position), which compresses the flow channel and has a certain effect on blocking particle backflow. The magnetic surface of the inner divertor leg 2 is widened at the bottom position (similar to the foot position). The divertor target plate is placed here, which is beneficial to disperse heat flow and reduce the peak load of the target plate.

[0057] The external divertor leg 3 is an arc shape that bulges to the right (similar to a right bracket), which can increase the leg length. The magnetic surface of the external divertor leg 3 is contracted at the middle position (similar to the knee position), which compresses the flow channel and has a certain effect on blocking particle backflow. The magnetic surface of the external divertor leg 3 is widened at the bottom position (similar to the foot position). The divertor target plate is placed here, which is conducive to dispersing heat flow and reducing the peak load of the target plate.

[0058] Furthermore, half the distance between the left and right boundaries of the main plasma region 1 is equal to the small radius of the plasma; the length of the inner divertor leg can reach 2 to 3 times the small radius of the plasma; the length of the outer divertor leg can reach 2 to 3 times the small radius of the plasma; while the length of the legs of a conventional divertor configuration is usually less than one time the small radius of the plasma. Therefore, the divertor legs of the divertor configuration proposed in this embodiment are significantly longer than those of a conventional divertor leg, which increases the distance of the plasma from point X to the target plate, thereby creating conditions for radiating more energy.

[0059] Furthermore, such as Figure 2 As shown, the gourd-shaped divertor proposed in this embodiment also includes: an inner target plate 21, an outer target plate 22, a shielding module 23, a strong-field side shielding module 24, a weak-field side shielding module 25, neutron linear transport channels (26, 27, 28), and a vacuum chamber section 29, etc. The inner target plate 21 is installed at the bottom of the inner divertor leg 2, and the outer target plate 22 is installed at the bottom of the outer divertor leg 3. Figure 2 As shown, the gourd-shaped divertor configuration, with its arc-shaped divertor legs, increases the distance between point X and the impact point. This reduces the heat load reaching the target plate by increasing radiation, and the magnetic surface expansion near the impact point further disperses heat flow, further reducing the peak heat load around the target plate. The magnetic surface contraction at the midpoint of the inner and outer divertor legs compresses the flow channel, effectively preventing particle backflow. The outward protrusion of the inner and outer divertor legs, combined with the use of a shielding module, blocks the direct bombardment of the inner and outer target plates by neutrons, thus providing excellent protection for the divertor. Furthermore, the divertor shielding module reduces high-energy neutron leakage, improves neutron utilization, and is beneficial for increasing the tritium multiplication rate (TBR).

[0060] This embodiment also proposes a configuration construction method for the aforementioned gourd-shaped divertor, such as... Figure 3 As shown, the method mainly includes the following steps:

[0061] Step 1: Arrange the poloidal field coils, i.e., the positions of the poloidal field coils.

[0062] Step 2: Based on the magnitude of the plasma current, apply a certain combination of currents to the poloidal field coils of the layout to obtain the configuration of the gourd-shaped divertor.

[0063] Furthermore, the poloidal field coils in this embodiment include a central solenoid coil, a divertor coil, and a shaping field coil. The central solenoid coil and the shaping field coil are primarily used to constrain the shape of the main plasma region and maintain its evolution. The divertor coil is crucial for forming the gourd-shaped divertor configuration and mainly includes an internal divertor coil located between the inner and outer divertor legs, and an external divertor coil located outside the vacuum chamber. The arrangement of the poloidal field coils should satisfy the following: the center point of the poloidal cross-section of the internal divertor coil should be located to the left of the vertical line passing through point X, and the distance between the center point of the poloidal cross-section of the internal divertor coil and this vertical line should be less than 0.25 times the width of the poloidal cross-section of the internal divertor coil. The vertical position of the center point of the poloidal section of the internal divertor coil can be adjusted appropriately according to the vertical height requirements of the neutron shielding module. Simultaneously, the center point of the poloidal section of the internal divertor coil should be located near the horizontal line passing through the point of maximum curvature of the divertor leg, with an upper and lower offset distance less than 1.0 times the height of the poloidal section of the internal divertor coil. Ideally, the center point of the poloidal section of the internal divertor coil should be on the same horizontal line as the point of maximum curvature of the divertor leg. Similarly, the center point of the poloidal section of the coil in the central solenoid coil corresponding to the middle position of the divertor leg should be located near the horizontal line passing through the center point of the poloidal section of the internal divertor coil, with an upper and lower offset distance less than 0.5 times the height of the poloidal section of the internal divertor coil. Ideally, the center point of the poloidal section of the coil in the central solenoid coil corresponding to the middle position of the divertor leg should be on the same horizontal line as the center point of the poloidal section of the internal divertor coil. The center point of the poloidal section of the coil corresponding to the bottom of the divertor leg in the central solenoid coil should be located near the horizontal line passing through the impact point, with its upper and lower offset distances less than a threshold. Ideally, the center point of the poloidal section of the coil corresponding to the bottom of the divertor leg in the central solenoid coil should be on the same horizontal line as the impact point. The center point of the poloidal section of the external divertor coil should be located to the left of the straight line passing through the center point of the poloidal section of the internal divertor coil and point X. Furthermore, the horizontal distance from the center point of the poloidal section of the external divertor coil closest to this straight line should be less than 1.0 times the width of the poloidal section of that coil. The layout of other poloidal field coils can follow conventional methods.

[0064] The outward protrusion of the inner and outer divertor legs allows the divertor target plate to be positioned below the inner divertor coil, making the divertor design more compact and minimizing the risk of direct neutron bombardment, thus reducing the difficulty of engineering design for fusion reactor divertors.

[0065] Specifically, such as Figure 4As shown, the central solenoid coil includes coil 5, coil 6, coil 7, coil 8, coil 9, coil 10, and coil 11; the divertor coil includes coil 12, coil 13, coil 14, coil 18, coil 15, and coil 20 (i.e., the internal divertor coil). The shaping field coil includes coil 14, coil 15, coil 16, and coil 17. Coils 10 and 11 in the central solenoid and the lower divertor coil (coils 14 and 19) and internal divertor coil (coil 20) in the divertor coil are key to constructing the gourd-shaped divertor configuration.

[0066] The center point of the poloidal section of the internal divertor coil should be located to the left of the vertical line passing through point X4, and the horizontal distance between the center point of the poloidal section of the internal divertor coil and the vertical line should be less than 0.25 times the width of the poloidal section of the internal divertor coil. The vertical position of the center point of the poloidal section of the internal divertor coil can be adjusted appropriately according to the vertical height requirements of the neutron shielding module, but the center point of the poloidal section of the internal divertor coil should be located near the horizontal line passing through the point of maximum curvature of the divertor leg, and the upper and lower offset distance (i.e., the distance between the center point of the poloidal section of the internal divertor coil and the horizontal line) should be less than 1.0 times the height of the poloidal section of the internal divertor coil; preferably, the center point of the poloidal section of the internal divertor coil and the point of maximum curvature of the divertor leg (i.e., the middle position of divertor leg 2 and divertor leg 3) are on the same horizontal line.

[0067] The center point of the pole section of the sixth coil 10 should be located near the horizontal line passing through the center point of the pole section of the inner divertor coil, and the upper and lower offset distance (i.e. the distance between the center point of the pole section of the sixth coil 10 and the horizontal line) should be less than 0.5 times the height of the pole section of the inner divertor coil; preferably, the center point of the pole section of the sixth coil 10 and the center point of the pole section of the inner divertor coil are on the same horizontal line.

[0068] The center point of the pole section of the seventh coil 11 should be located near the horizontal line passing through the impact point (target plate, i.e., the bottom of the divertor leg), and the upper and lower offset distances (i.e., the distance between the center point of the pole section of the seventh coil 11 and the horizontal line) should be less than a threshold value; preferably, the center point of the pole section of the seventh coil 11 and the impact point are on the same horizontal line.

[0069] The center point of the pole section of the fourteenth coil 18 should be located to the left of the straight line passing through the center point of the pole section of the internal divertor coil and point X, and the horizontal distance between the center point of the pole section of the fourteenth coil 18 and the straight line should be less than 1.0 times the width of the pole section of the fourteenth coil 18.

[0070] The arrangement of the remaining coils is not special and can be arranged in the same way as the conventional tokamak poloidal field coils, so I will not go into too much detail here.

[0071] Furthermore, in this embodiment, the current combination of the coils in the layout also needs to meet the following constraints: (1) the current loaded on the lower divertor coil (i.e., the fourteenth coil 18 and the fifteenth coil 19) and the inner divertor coil (i.e., the sixteenth coil 20) should be in the same direction as the plasma current; (2) the current loaded on the sixth coil 10, the seventh coil 11 and the thirteenth coil 17 should be in the opposite direction to the plasma current. This results in a special configuration where the inner divertor leg is an arc protruding to the left, the outer divertor leg is an arc protruding to the right, and the magnetic surface at the middle position of the inner and outer divertor legs contracts, while the magnetic surface near the impact point at the bottom position of the inner and outer divertor legs widens, i.e., a gourd-shaped divertor configuration.

[0072] It should be noted that, Figure 4 The poloidal field coil layout shown is only an example. In other alternative embodiments, other poloidal field coil layouts can also be used, as long as a gourd-shaped configuration can be obtained: the inner divertor leg is an arc protruding to the left, the outer divertor leg is an arc protruding to the right, and the magnetic surface at the middle position of the inner and outer divertor legs is contracted, while the magnetic surface at the bottom position of the inner and outer divertor legs is widened.

[0073] This embodiment also proposes a configuration construction system for the aforementioned gourd-shaped divertor, such as... Figure 5 As shown, the system mainly includes:

[0074] The coil layout unit arranges the poloidal coils according to the poloidal coil layout strategy. The specific poloidal coil layout strategy is the same as that described in the configuration construction method above, and will not be elaborated further here.

[0075] And a current loading unit, which, in conjunction with the magnitude of the plasma current, loads a certain combination of currents onto the arranged poloidal field coils to obtain the gourd-shaped divertor configuration.

[0076] Those skilled in the art will understand that embodiments of this application can be provided as methods, systems, or computer program products. Therefore, this application can take the form of a completely hardware embodiment, a completely software embodiment, or an embodiment combining software and hardware aspects. Furthermore, this application can take the form of a computer program product embodied on one or more computer-usable storage media (including but not limited to disk storage, CD-ROM, optical storage, etc.) containing computer-usable program code.

[0077] This application is described with reference to flowchart illustrations and / or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of this application. It will be understood that each block of the flowchart illustrations and / or block diagrams, and combinations of blocks in the flowchart illustrations and / or block diagrams, can be implemented by computer program instructions. These computer program instructions can be provided to a processor of a general-purpose computer, special-purpose computer, embedded processor, or other programmable data processing apparatus to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing apparatus, generate instructions for implementing the flowchart... Figure 1 One or more processes and / or boxes Figure 1 A device that provides the functions specified in one or more boxes.

[0078] These computer program instructions may also be stored in a computer-readable storage medium that can direct a computer or other programmable data processing device to function in a particular manner, such that the instructions stored in the computer-readable storage medium produce an article of manufacture including instruction means, which are implemented in a process Figure 1 One or more processes and / or boxes Figure 1 The function specified in one or more boxes.

[0079] These computer program instructions may also be loaded onto a computer or other programmable data processing equipment to cause a series of operational steps to be performed on the computer or other programmable equipment to produce a computer-implemented process, thereby providing instructions that execute on the computer or other programmable equipment for implementing the process. Figure 1 One or more processes and / or boxes Figure 1 The steps of the function specified in one or more boxes.

[0080] The specific embodiments described above further illustrate the purpose, technical solution, and beneficial effects of the present invention. It should be understood that the above description is only a specific embodiment 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 within the scope of protection of the present invention.

Claims

1. A method for constructing the configuration of a gourd-shaped divertor suitable for compact fusion reactors, characterized in that, The configuration of the gourd-shaped divertor includes a main plasma region, a divertor region, and point X. The main plasma region is the fusion reaction area enclosed by the outermost closed magnetic surface. Point X is the boundary between the main plasma region and the divertor region. The divertor region consists of inner divertor legs and outer divertor legs. Both the inner and outer divertor legs are outwardly convex arcs. The magnetic surface at the middle position of the inner and outer divertor legs contracts, and the magnetic surface at the bottom position of the inner and outer divertor legs widens. A divertor target plate is arranged at the bottom position of the inner and outer divertor legs. The configuration construction method includes: Arrange the positions of the poloidal field coils; Based on the magnitude of the plasma current, a corresponding current combination is applied to the poloidal field coil to obtain the gourd-shaped divertor configuration; the poloidal field coil includes a central solenoid coil, a divertor coil, and a shaping field coil. The central solenoid coil and the shaping field coil are used to constrain the shape of the main plasma region and maintain the evolution of the plasma region; The divertor coil includes an inner divertor coil located between the inner divertor leg and the outer divertor leg, and an outer divertor coil located outside the vacuum chamber, for forming the configuration of the divertor region; the positional arrangement of the poloidal field coils should satisfy: The center point of the pole section of the internal divertor coil is located to the left of the vertical line passing through point X, and the distance between the center point of the pole section of the internal divertor coil and the vertical line is less than 0.25 times the width of the pole section of the internal divertor coil.

2. The configuration construction method according to claim 1, characterized in that, Half the distance between the left and right boundaries of the main plasma region is equal to the small radius of the plasma.

3. The configuration construction method according to claim 1, characterized in that, The length of the inner divertor leg or the outer divertor leg is equal to 2 to 3 times the small radius of the plasma.

4. The configuration construction method according to any one of claims 1-3, characterized in that, The position of the center point of the poloidal section of the internal divertor coil in the vertical direction can be adjusted according to the vertical height requirements of the neutron shielding module. At the same time, the center point of the poloidal section of the internal divertor coil is located near the horizontal line passing through the point of maximum curvature of the divertor leg, and the upper and lower offset distances are less than 1.0 times the height of the poloidal section of the internal divertor coil.

5. The configuration construction method according to claim 4, characterized in that, The center point of the poloidal section of the internal divertor coil is on the same horizontal line as the point of maximum curvature of the divertor leg.

6. The configuration construction method according to claim 4, characterized in that, The center point of the pole section of the coil corresponding to the middle position of the divertor leg in the central solenoid coil is located near the horizontal line passing through the center point of the pole section of the inner divertor coil, and the upper and lower offset distance is less than 0.5 times the height of the pole section of the inner divertor coil.

7. The configuration construction method according to claim 6, characterized in that, The center point of the polar section of the coil corresponding to the middle position of the divertor leg in the central solenoid coil is on the same horizontal line as the center point of the polar section of the internal divertor coil.

8. The configuration construction method according to claim 6, characterized in that, The center point of the pole section of the coil corresponding to the bottom of the divertor leg in the central solenoid coil is located near the horizontal line passing through the impact point, and the upper and lower offset distances are less than the threshold.

9. The configuration construction method according to claim 8, characterized in that, The center point of the polar section of the coil corresponding to the bottom of the divertor leg in the central solenoid coil is on the same horizontal line as the impact point.

10. The configuration construction method according to claim 8, characterized in that, The center point of the pole section of the external divertor coil should be located to the left of the straight line passing through the center point of the pole section of the internal divertor coil and the X point, and the horizontal distance from the center point of the pole section of the external divertor coil closest to the straight line to the straight line should be less than 1.0 times the width of the pole section of that coil.

11. A configuration construction system for a gourd-shaped divertor suitable for compact fusion reactors, characterized in that, The configuration of the gourd-shaped divertor includes a main plasma region, a divertor region, and point X. The main plasma region is the fusion reaction area enclosed by the outermost closed magnetic surface. Point X is the boundary between the main plasma region and the divertor region. The divertor region consists of inner divertor legs and outer divertor legs. Both the inner and outer divertor legs are outwardly convex arcs. The magnetic surface contracts at the middle position of the inner and outer divertor legs and widens at the bottom position. A divertor target plate is arranged at the bottom position of the inner and outer divertor legs. The configuration construction system includes: A coil layout unit, wherein the coil layout unit arranges the positions of the poloidal field coils; And, a current loading unit, which, in combination with the magnitude of the plasma current, loads a corresponding combination of currents onto the poloidal field coil to obtain the gourd-shaped divertor configuration; The poloidal field coil includes a central solenoid coil, a divertor coil, and a shaping field coil; The central solenoid coil and the shaping field coil are used to constrain the shape of the main plasma region and maintain the evolution of the plasma region; The divertor coil includes an inner divertor coil located between the inner divertor leg and the outer divertor leg, and an outer divertor coil located outside the vacuum chamber, for forming the configuration of the divertor region; the positional arrangement of the poloidal field coils should satisfy: The center point of the pole section of the internal divertor coil is located to the left of the vertical line passing through point X, and the distance between the center point of the pole section of the internal divertor coil and the vertical line is less than 0.25 times the width of the pole section of the internal divertor coil.

12. An electronic device comprising a memory and a processor, wherein the memory stores a computer program, characterized in that, When the processor executes the computer program, it implements the steps of the method according to any one of claims 1-10.

13. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by a processor, it implements the steps of the method according to any one of claims 1-10.

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