Method and apparatus for determining state information in reaction chamber during nuclear fusion reaction process

Abstract

Provided in the present application are a method and apparatus for determining state information in a reaction chamber during a nuclear fusion reaction process. The method comprises: acquiring diagnostic information of a nuclear fusion reaction apparatus during a nuclear fusion reaction process; on the basis of the diagnostic information, determining a target configuration from among a plurality of alternative configurations of a plasma, wherein the plurality of alternative configurations comprise a single-loop configuration, a first double-loop configuration and a second double-loop configuration, the first double-loop configuration including two independent plasma loops, and the second double-loop configuration including two plasma loops located in a closed magnetic surface; and on the basis of the diagnostic information, and in view of a response feature set corresponding to the target configuration, performing equilibrium reconstruction processing, so as to determine target state information in a reaction chamber, wherein the response feature set comprises a plurality of response features reflecting the relationship between the diagnostic information and state information. The method reduces the limitations in determining the state information in the reaction chamber during the nuclear fusion reaction process.

Description

Methods and devices for determining the state information inside the reaction chamber during nuclear fusion reaction

[0001] This application claims priority to Chinese Patent Application No. 202411529008.7, filed on October 30, 2024, entitled “Method and Apparatus for Determining State Information in a Reactor Chamber During a Nuclear Fusion Reaction”, the entire contents of which are incorporated herein by reference. Technical Field

[0002] This application relates to the field of nuclear fusion technology, and in particular to a method for determining the state information inside the reaction chamber during a nuclear fusion reaction. It also relates to a device for determining the state information inside the reaction chamber during a nuclear fusion reaction, a computing device, a computer-readable storage medium, and a computer program product. Background Technology

[0003] Nuclear fusion technology has been widely studied due to its advantage of producing large amounts of clean energy. Nuclear fusion reaction requires the use of nuclear fusion reactors (such as tokamak devices) to control the plasma and bring it to the fusion conditions.

[0004] Typically, it is necessary to determine the state information (such as plasma morphology and magnetic field distribution) within the reaction chamber at various moments during the nuclear fusion reaction. Based on the actual state information within the reaction chamber at the current moment and the subsequent requirements of the nuclear fusion reaction, information such as the current applied to the corresponding components in the nuclear fusion reactor can be adjusted.

[0005] However, the current methods for determining the state information within the reaction chamber during a nuclear fusion reaction are quite limited, making it difficult to accurately determine this state information at every moment during the nuclear fusion reaction process. Summary of the Invention

[0006] This application provides a method for determining the state information inside the reaction chamber during a nuclear fusion reaction, which can accurately determine the corresponding state information inside the reaction chamber at various times, reducing the limitations of determining the state information inside the reaction chamber during a nuclear fusion reaction. This application also relates to a device for determining the state information inside the reaction chamber during a nuclear fusion reaction, a computing device, a computer-readable storage medium, and a computer program product.

[0007] According to a first aspect of the embodiments of this application, a method for determining state information within a reaction chamber during a nuclear fusion reaction is provided, the method comprising:

[0008] To obtain diagnostic information of the nuclear fusion reactor during the nuclear fusion process;

[0009] Based on the diagnostic information, a target configuration is determined from a variety of alternative configurations of the plasma; wherein, the variety of alternative configurations includes a single-ring configuration, a first double-ring configuration, and a second double-ring configuration, wherein the first double-ring configuration contains two independent plasma rings, and the second double-ring configuration contains two plasma rings located in a closed magnetic surface.

[0010] Based on the diagnostic information and the response feature set corresponding to the target configuration, a balance inversion process is performed to determine the target state information within the reaction chamber; wherein, the response feature set includes multiple response features reflecting the relationship between the diagnostic information and the state information, and the target state information includes the distribution information of plasma and the distribution information of magnetic field in the reaction chamber.

[0011] According to a second aspect of the present application, a device for determining state information within a reaction chamber during a nuclear fusion reaction is provided, the device comprising:

[0012] The acquisition module is used to acquire diagnostic information of the nuclear fusion reactor during the nuclear fusion reaction process;

[0013] The first determining module is used to determine the target configuration among a variety of alternative configurations of plasma based on the diagnostic information; wherein the variety of alternative configurations includes a single-ring configuration, a first double-ring configuration, and a second double-ring configuration, wherein the first double-ring configuration contains two independent plasma rings, and the second double-ring configuration contains two plasma rings located in a closed magnetic surface.

[0014] The second determining module is used to perform equilibrium inversion processing based on the diagnostic information and the response feature set corresponding to the target configuration to determine the target state information in the reaction chamber; wherein, the response feature set includes multiple response features reflecting the relationship between the diagnostic information and the state information, and the target state information includes the distribution information of plasma and the distribution information of magnetic field in the reaction chamber.

[0015] According to a third aspect of this application, a computing device is provided, comprising: a memory and a processor;

[0016] The memory is used to store computer programs / instructions, and the processor is used to execute the computer programs / instructions. When the programs / instructions are executed by the processor, they implement the steps of the above method.

[0017] According to a fourth aspect of this application, a computer-readable storage medium is provided that stores a computer program / instructions, which, when executed by a processor, implement the steps of the above-described method.

[0018] According to a fifth aspect of this application, a computer program product is provided, comprising a computer program / instructions that, when executed by a processor, implement the steps of the above-described method.

[0019] In this application, corresponding response feature sets are set for the single-ring configuration, the first double-ring configuration, and the second double-ring configuration that change during the nuclear fusion reaction. Based on the diagnostic information of the nuclear fusion reactor during the nuclear fusion reaction, the target configuration corresponding to the current state of the nuclear fusion reactor can be determined from these multiple alternative configurations. Then, based on the response feature set corresponding to the target configuration, equilibrium inversion processing can be performed to obtain the target state information in the current reaction chamber, that is, the plasma distribution information and the magnetic field distribution information. In this way, the corresponding state information in the reaction chamber can be accurately determined at each moment in the nuclear fusion reaction process, reducing the limitations of determining the state information in the reaction chamber during the nuclear fusion reaction. Attached Figure Description

[0020] Figure 1 is a flowchart of a method for determining the state information inside a nuclear fusion reaction process according to an embodiment of this application.

[0021] Figure 2 is a schematic diagram of a first double-ring configuration provided in an embodiment of this application;

[0022] Figure 3 is a schematic diagram of a second double-ring configuration provided in an embodiment of this application;

[0023] Figure 4 is a schematic diagram of a single-ring configuration provided in an embodiment of this application;

[0024] Figure 5 is a schematic diagram of the structure of a response matrix provided in an embodiment of this application;

[0025] Figure 6 is a schematic diagram of another response matrix structure provided in an embodiment of this application;

[0026] Figure 7 is a schematic diagram of another response matrix provided in an embodiment of this application;

[0027] Figure 8 is a flowchart of a balance inversion process provided in an embodiment of this application;

[0028] Figure 9 is a simplified schematic diagram of a balance inversion process provided in an embodiment of this application;

[0029] Figure 10 is a simplified flowchart of determining a target configuration according to an embodiment of this application;

[0030] Figure 11 is a schematic diagram of a device for determining the state information inside a nuclear fusion reaction process according to an embodiment of this application.

[0031] Figure 12 is a structural block diagram of a computing device provided in an embodiment of this application. Detailed Implementation

[0032] Many specific details are set forth in the following description to provide a full understanding of this application. However, this application can be implemented in many other ways different from those described herein, and those skilled in the art can make similar extensions without departing from the spirit of this application; therefore, this application is not limited to the specific embodiments disclosed below.

[0033] The terminology used in one or more embodiments of this application is for the purpose of describing particular embodiments only and is not intended to limit the scope of the one or more embodiments of this application. The singular forms “a,” “the,” and “the” used in one or more embodiments of this application and the appended claims are also intended to include the plural forms unless the context clearly indicates otherwise. It should also be understood that the term “and / or” used in one or more embodiments of this application refers to and includes any or all possible combinations of one or more associated listed items. The term “at least one” in one or more embodiments of this application means “one or more,” and “a plurality of” means “two or more.” The term “comprising” is an open-ended description and should be understood as “including but not limiting,” and may include other content in addition to what has been described.

[0034] It should be understood that although the terms "first," "second," etc., may be used to describe various information in one or more embodiments of this application, such information should not be limited to these terms. These terms are only used to distinguish information of the same type from one another. For example, "first" may also be referred to as "second" without departing from the scope of one or more embodiments of this application, and similarly, "second" may also be referred to as "first." Depending on the context, the word "if," as used herein, may be interpreted as "when," "in response to a determination," or "when," or "in the event of a determination."

[0035] In the field of nuclear fusion technology, to achieve efficient and stable nuclear fusion reactions, it is necessary to ensure the equilibrium of the plasma in the reaction chamber (also known as the vacuum chamber) of the nuclear fusion reactor (such as a tokamak) and to control the plasma's configuration (i.e., position and shape) according to the reaction requirements. This equilibrium can refer to equilibrium in the sense of magnetohydrodynamics, that is, from a macroscopic perspective, the plasma is regarded as a conductive fluid that reaches an equilibrium state under the influence of a magnetic field. This configuration control needs to be based on the actual configuration of the plasma at each moment, and also needs to be combined with various additional information. Therefore, it is necessary to determine the actual configuration of the plasma at each moment and these various additional information. These various additional information may include information such as the magnetic field distribution, current distribution, pressure distribution, and safety factor (usually represented by q) in the reaction chamber. The safety factor is defined as the number of rotations of the magnetic field lines in the circumferential direction along the polar direction. The plasma configuration belongs to the plasma distribution information. In the embodiments of this application, the plasma distribution information and these various additional information are collectively referred to as the state information within the reaction chamber.

[0036] This additional information can be divided into macroscopic parameters of the plasma and local equilibrium parameters. For example, the macroscopic parameters may include the plasma's outermost closed magnetic surface (LCFS), specific pressure (usually denoted by β), and internal inductance (which can be expressed as l). i This information includes details such as the magnetic surface structure, pressure profile, and current density profile. The outermost closed magnetic surface of the plasma refers to the interface between the plasma and the external vacuum region, where the closed magnetic field lines form a magnetic layer surrounding the plasma. Specific pressure is the ratio of plasma pressure to magnetic pressure, and it measures the relative strength of the plasma's thermodynamic effects relative to the magnetic confinement effect. Internal inductance describes the plasma current distribution and is related to the plasma current profile; specifically, it is defined as the total magnetic flux divided by the total plasma current. The boundary safety factor is defined as the ratio of the number of rotations of the circumferential field lines on a magnetic surface to the poloidal radius of that magnetic surface. Maintaining a sufficient boundary safety factor (e.g., avoiding a q value below a certain critical value) can improve the plasma confinement performance.

[0037] Since the state information within the reaction chamber is difficult to measure directly, an alternative approach is to rely on plasma equilibrium reconstruction. This reconstruction uses indirect measurement data (such as diagnostic information from the fusion reactor) to reconstruct the equilibrium position and shape of the plasma within the reaction chamber. Various diagnostic components can be incorporated into the fusion reactor to diagnose it and determine various diagnostic information. Diagnosing the fusion reactor involves detecting various parameters of the reactor; in the field of fusion technology, this detection operation is commonly referred to as diagnosis. For example, diagnostic components may include magnetic flux loops, magnetic probes, and Roco coils. The diagnostic information obtained from diagnosing the fusion reactor may include the current in the discharge coil, the plasma current, and the eddy currents in the reaction chamber. These eddy currents can be induced eddy currents generated on the inner wall of the reaction chamber under the influence of the discharge coil current and the plasma current. The discharge coil can also be called an active coil.

[0038] Plasma equilibrium reconstruction can be achieved using an inversion method, referred to below as equilibrium inversion processing. This process involves reconstructing plasma equilibrium by applying equilibrium inversion processing to diagnostic information. By fitting the magnetic field and flux signals around the nuclear fusion reactor, the poloidal flux distribution satisfying the Grad-Shafrnaov (GS) equilibrium equations is solved, reconstructing the plasma equilibrium configuration and providing real-time configuration control parameters. The GS equilibrium equations describe the equilibrium state of plasma under ideal conditions, neglecting resistance and particle effects, under the combined influence of its own current and an applied magnetic field. This equation is a nonlinear partial differential equation, formally relating the plasma's pressure distribution, current density distribution, and magnetic field configuration. The GS equilibrium equations provide a mathematical framework that represents how the plasma achieves force equilibrium through pressure gradient forces and Lorentz forces. The equilibrium equations are typically solved numerically using a least-squares fitting algorithm. This algorithm finds estimates of the magnetic field distribution and other relevant parameters that minimize the deviation between the plasma equilibrium state calculated using these parameters and experimental observations or advanced simulation data. Based on these estimates, the state information within the reactor chamber can be obtained.

[0039] In the Sino-UNIted Spherical Tokamak (SUNIST), nuclear fusion is achieved by directly generating a plasma ring and heating the plasma to the fusion reaction temperature using an external energy source. Currently, the single-ring equilibrium inversion method ERST (Equilibrium Reconstruction for Spherical Tokamak) is used to reconstruct the plasma equilibrium of SUNIST. This method, based on limited magnetic field measurement data, uses numerical algorithms to inversely calculate the current distribution and other plasma parameters within the entire plasma, thereby obtaining the plasma equilibrium configuration.

[0040] The Sino-UNIted Spherical Tokamak-2 (SUNIST-2) is my country's strongest spherical tokamak in terms of magnetic field and plasma parameters, primarily used to explore magnetic reconnection heating technology. This technology involves inducing two plasma rings in the reaction chamber and then merging and compressing them into a single main plasma ring. During this process, the magnetic field generated by the plasma rings undergoes large-scale magnetic reconnection, rapidly and efficiently heating the plasma to the fusion reaction temperature to achieve nuclear fusion. During the fusion and compression process, the plasma state changes drastically and its configuration is complex and variable. Therefore, determining the plasma equilibrium at various moments (e.g., determining plasma distribution and ensuring a stable plasma state) is quite complex for this nuclear fusion device. For example, determining the plasma equilibrium requires considering internal and external separation lines, the magnetic configuration of single or multiple magnetic axes, and eddy currents in the reaction chamber. Correspondingly, plasma equilibrium reconstruction for this nuclear fusion device also requires considering this information. Currently, there is no suitable scheme for plasma equilibrium reconstruction for this nuclear fusion reactor, so the state information inside the reactor is difficult to determine effectively, and the current determination of the state information inside the reactor has high limitations.

[0041] This application provides a method for determining the state information inside the reactor chamber during a nuclear fusion reaction. This method can be applied to SUNIST or SUNIST-2 to determine the state information inside the reactor chamber at various times, achieving accurate determination of the corresponding state information at each moment and reducing the limitations of determining the state information inside the reactor chamber during a nuclear fusion reaction. This application also relates to a device for determining the state information inside the reactor chamber during a nuclear fusion reaction, a computing device, a computer-readable storage medium, and a computer program product, which will be described in detail below. This method can be executed by the determining device or the computing device, which can be devices with significant computing power, such as servers, desktop computers, laptops, etc. The determining device and computing device can also have a display function to display the determined state information; or a communication function to send the determined state information to other devices for display.

[0042] Figure 1 is a flowchart of a method for determining state information within a reaction chamber during a nuclear fusion reaction, provided by an embodiment of this application. This method can be applied to an information determination device. As shown in Figure 1, the method may include steps 102 to 106.

[0043] Step 102: Obtain diagnostic information of the nuclear fusion reactor during the nuclear fusion reaction process.

[0044] The diagnostic information may include current information from the discharge coils in the nuclear fusion reactor, plasma current information in the reaction chamber, and induced eddy current information in the reaction chamber. The discharge coils in the nuclear fusion reactor may include a central solenoid coil, a poloidal magnetic field coil, and a circumferential magnetic field coil located outside the reaction chamber, as well as a merging-compression (MC) coil located inside the reaction chamber. The magnetic field generated by the MC coil can be used to drive the two plasma loops at both ends of the reaction chamber towards the center, achieving merging compression.

[0045] Multiple diagnostic components can be installed on a nuclear fusion reactor to diagnose the reactor and obtain corresponding diagnostic information. These diagnostic components may include plasma current Rococo coils, flux loops, magnetic probes, saddle coils, contramagnetic coils, and compensation coils, with a single-turn loop being a type of flux loop. The magnetic probe, flux loop, and saddle coil are used to measure magnetic fields and flux, the contramagnetic coil is used to measure contramagnetic information, and the Rococo coil is used to measure current (including plasma current and discharge coil current). Contramagnetism refers to the state of the plasma when the circumferential magnetic field within the plasma is lower than the vacuum field; in this case, the plasma is contramagnetic. Paramagnetism refers to the state of the plasma when the circumferential magnetic field within the plasma is stronger than the vacuum field; in this case, the plasma is paramagnetic. For example, the magnetic probe may include an array of circumferential magnetic probes, a radial array of magnetic probes, and a poloidal array of magnetic probes. Two Rococo coils can be arranged inside and outside the reaction chamber, one for measuring the plasma current and the other for measuring the total current of the induced eddy currents in the plasma and the reaction chamber. In this embodiment, the information determination device can perform inversion using real diagnostic diamagnetic and eddy current information, without the need to set simulated diamagnetic and eddy current information, thus ensuring a better inversion effect.

[0046] During the operation of the nuclear fusion reactor (i.e., the process of nuclear fusion reaction), each diagnostic component can operate to detect various information about the nuclear fusion reactor at different times. An information determination device can connect to each diagnostic component to obtain diagnostic information about the nuclear fusion reactor determined by each diagnostic component; this connection can include a wireless communication connection or a wired connection. The information determination device can continuously acquire diagnostic information from each diagnostic component, and based on the diagnostic information acquired at each time point, it can execute the method for determining the state information within the reaction chamber provided in the embodiments of this application.

[0047] Step 104: Determine the target configuration from multiple alternative configurations of the plasma based on diagnostic information; wherein, the multiple alternative configurations include a single-ring configuration, a first double-ring configuration, and a second double-ring configuration, wherein the first double-ring configuration contains two independent plasma rings, and the second double-ring configuration contains two plasma rings located in a closed magnetic surface.

[0048] During a nuclear fusion reaction, the plasma configuration can change between several configurations. The conditions required for the plasma to reach equilibrium differ under different configurations, and the information needed for plasma equilibrium reconstruction also varies. Therefore, the information determination device can first determine the target configuration of the current plasma based on acquired diagnostic information, and then perform plasma equilibrium reconstruction based on the information corresponding to that target configuration.

[0049] In some embodiments, the nuclear fusion reactor is based on magnetic reconnection heating technology, which fuses and compresses two plasma rings in the reaction chamber to achieve a nuclear fusion reaction. During this nuclear fusion reaction, the plasma configuration can sequentially change between a first double-ring configuration, a second double-ring configuration, and a single-ring configuration. The first double-ring configuration can be called a droplet configuration, and the second double-ring configuration can be called a doublet configuration. The first double-ring configuration can be the configuration during the generation of the two plasma rings, the second double-ring configuration can be the configuration during the fusion of the two plasma rings, and the single-ring configuration can be the configuration after the two plasma rings have completed fusion. In this application embodiment, all possible configurations of the plasma during the process are referred to as alternative configurations, and at any given time, the plasma configuration is one of these alternative configurations. In some embodiments, the shape of the plasma can be changed after it becomes a single-ring configuration, such as changing from an equilateral triangular single-ring configuration to a negative triangular single-ring configuration.

[0050] Figure 2 is a schematic diagram of a first double-ring configuration provided in an embodiment of this application; Figure 3 is a schematic diagram of a second double-ring configuration provided in an embodiment of this application; and Figure 4 is a schematic diagram of a single-ring configuration provided in an embodiment of this application. Figures 2 to 4 show the distribution of plasma in the reaction chamber 10. The lines represent magnetic field lines, and the thickened lines represent the outermost closed magnetic surface of the plasma. This outermost closed magnetic surface is surrounded by closed magnetic field lines, and the magnetic field strength is the same at all positions along the same magnetic field line. As shown in Figure 2, the first double-ring configuration includes two independent plasma rings, which can be located near the two ends of the longitudinal direction of the reaction chamber, such as the two plasma rings located within the enclosed regions of closed magnetic surfaces M11 and M12, respectively. As shown in Figure 3, the second double-ring configuration includes two plasma rings located within a closed magnetic surface M20. These two plasma rings are closer to the equatorial plane (i.e., the mid-plane in the longitudinal direction) of the reaction chamber 10 compared to Figure 2, such as the two plasma rings located within the enclosed regions of closed magnetic surfaces M21 and M22, respectively. As shown in Figure 4, the single-ring configuration includes a plasma ring located in the middle region of the reaction chamber 10 in the longitudinal direction, such as within the area surrounded by the closed magnetic surface M3.

[0051] In some implementations, since the number and location of plasma rings differ among different candidate configurations, the information determination device can determine the number and location of plasma rings based on acquired diagnostic information to determine the target configuration. For example, the information determination device can determine the target configuration by identifying the outermost closed magnetic surface of the plasma.

[0052] Step 106: Based on the diagnostic information and the response feature set corresponding to the target configuration, perform equilibrium inversion processing to determine the target state information in the reaction chamber; wherein, the response feature set includes multiple response features that reflect the relationship between the diagnostic information and the state information in the reaction chamber, and the target state information includes the distribution information of plasma and the distribution information of magnetic field in the reaction chamber.

[0053] In this embodiment, the information determination device reconstructs plasma equilibrium through inversion. Based on the obtained diagnostic information and the relationship that plasma equilibrium must satisfy, it determines the state information within the reaction chamber. In this embodiment, the state information determined through plasma equilibrium reconstruction is referred to as the target state information. The target state information includes the distribution information of plasma and the distribution information of magnetic field in the reaction chamber. The plasma distribution information may include plasma configuration information, current distribution information (such as current density distribution information), and pressure distribution information, etc. The magnetic field distribution information may include the distribution information of magnetic field lines and magnetic flux at various locations in the reaction chamber. This target state information can be determined based on the system parameters that the nuclear fusion reactor should possess at plasma equilibrium. Such system parameters may include parameters such as the polynomial coefficients of the poloidal current term, the polynomial coefficients of the pressure term, the correlation coefficient of the passive conductor current, the correlation coefficient of the vertical displacement of plasma, and the correlation coefficient of the discharge coil current. The passive conductor may include the inner wall of the reaction chamber, and the passive conductor current includes the eddy currents of the inner wall of the reaction chamber. The vertical displacement refers to the displacement of the plasma ring in the longitudinal direction of the reaction chamber.

[0054] In this embodiment, the relationships required for plasma equilibrium are characterized by a response feature set, which includes multiple response features, each affecting the diagnostic information corresponding to the state information. The response feature set can be represented as a matrix, i.e., it can be a response matrix. This response matrix is ​​used to predict or model the expected response patterns in the observed signal due to specific stimuli, and is also related to the inverse modeling of plasma dynamic equilibrium. The response features in the response matrix can cause the plasma to return from an unbalanced state to an equilibrium state.

[0055] During a nuclear fusion reaction, the diagnostic information y can satisfy the target formula: y = A(x) × θ. Here, A(x) represents the response matrix, θ represents the system parameters of the nuclear fusion reactor, and y and θ can also be represented in matrix form. x represents the system state, which can include magnetic flux information at various locations within the reaction chamber, such as x = ψ(R, Z), where ψ represents the magnetic flux, R represents the radial direction of the reaction chamber, and Z represents the axial direction (i.e., longitudinal direction) of the reaction chamber. The information determination device can acquire the contents of y and A(x), and based on this target formula, reverse-engineer the system parameters of the nuclear fusion reactor. Then, based on these system parameters, the target state information within the reaction chamber can be determined.

[0056] For example, the system parameter θ in the objective formula may include: polynomial coefficients of the poloidal current term. Pressure term polynomial coefficients Passive conductor current Related items, active coil current Related terms and vertical displacement δz related terms. Diagnostic information y may include: diagnostic information of the flux loop. Diagnostic information from magnetic probes Plasma current I p Constraint information for regularization coefficients α and β Inverse magnetic flux information ψ dia Safety factor information q0 at the magnetic axis, and constraint information of eddy currents. Single-point constraint information ψ bry Multi-point constraint information ψ topo Constraint information of external coils Both the single-point constraint information and the multi-point topological constraint information belong to the category of magnetic surface topological constraint information. These constraint information specifications define the conditions that the plasma and magnetic field in the reaction chamber must meet in various aspects; the specific content of the constraint information may differ at different times. The various information included in the matrix-form system parameters θ and diagnostic information y can be arranged sequentially along the column direction.

[0057] The magnetic axis is the point where the plasma magnetic flux is at its maximum. In the embodiments of this application, the magnetic axis corresponds to the magnetic flux extremum point of the plasma. The magnetic flux at all positions around the magnetic flux extremum point is greater than or less than the magnetic flux at the magnetic flux extremum point. The magnetic field lines around the magnetic flux extremum point are closed and point in the center, forming a shape similar to the letter "O". This magnetic flux extremum point can also be called "point O".

[0058] In this embodiment, a corresponding response feature set can be pre-configured for each candidate configuration, and the response features in the response feature sets corresponding to different candidate configurations will have certain differences. In some embodiments, the response feature sets corresponding to the above-mentioned multiple candidate configurations all include: plasma magnetohydrodynamic equilibrium features, eddy current features of the reaction chamber, vertical displacement features of the plasma, and discharge coil features. Plasma magnetohydrodynamic equilibrium features include the pressure features and poloidal current features of the plasma ring, the total current features at each position of the plasma ring, regularization constraint features, contramagnetic constraint features, constraint features of the safety factor at the magnetic axis, and constraint features of the fixed boundary on the plasma. Among them, the fixed boundary refers to the single-point boundary constraint and the magnetic topological multi-point constraint.

[0059] For example, Figure 5 is a schematic diagram of the structure of a response matrix provided in an embodiment of this application. Figure 5 illustrates the response matrix corresponding to a single-ring configuration as an example. As shown in Figure 5, the pressure characteristics and poloidal current characteristics of the plasma ring can be represented by Gv×GG, where Gv represents the Green's function between the magnetic flux ring and the magnetic probe and the plasma, and GG represents the distribution information of the pressure term and the poloidal current term. The total current characteristic at each position of the plasma ring is represented by sum(GG), which can be obtained by adding various related terms based on the distribution information of the pressure term and the poloidal current term. The regularization constraint characteristic can be represented by polycoeffAeq, which is used to make the edges of the plasma current distribution region smoother. The dimagnetic constraint characteristic can be represented by the dimagnetic constraint matrix A. dia The constraint characteristics of the safety factor at the magnetic axis can be represented by the constraint matrix A of the safety factor at the magnetic axis. q0 The influence of fixed boundaries on plasma can be represented by the Green's function rfxbd2v between a single fixed point and the plasma. The characteristics of plasma magnetohydrodynamic equilibrium, eddy currents in the reaction chamber, and discharge coils all include topological features, such as the difference A between the Green's functions between the two fixed points and the plasma in Figure 5. topo1 The difference A between the Green's function of the two fixed points and the eddy current topo2 The difference A between the Green's function of the two fixed points and the external coil topo3 These three topological constraint matrices. The eddy current characteristics of the reaction chamber can also include the response information of the flux loop and magnetic probe to the eddy current (gfflmpvder), the total eddy current, and the component mode matrices A. eddy The Green's function rfxbd2der between a single fixed point and the eddy current. The vertical displacement characteristics of the plasma include the response information gredeltz of the flux loop and magnetic probe to the vertical displacement. The discharge coil characteristics include: the Green's function gpffl between the flux loop and the external coil, the Green's function gfflmpv between the magnetic probe and the external coil, and the Green's function rfxbd2pf between a single fixed point and the external coil.

[0060] The response feature set corresponding to the first double-ring configuration differs somewhat from the response feature set corresponding to the single-ring configuration shown in Figure 5. For example, the difference may lie only in the plasma magnetohydrodynamic equilibrium characteristics. For instance, the response feature set corresponding to the single-ring configuration includes the total current characteristics sum(GG) at each position of one plasma ring, while the total current characteristics at each position of the plasma ring corresponding to the first double-ring configuration include the total current characteristics at each position of both plasma rings. Figure 6 is a schematic diagram of another response matrix structure provided in an embodiment of this application. Figure 6 shows the response matrix corresponding to the first double-ring configuration. As shown in Figure 6, the total current characteristics corresponding to the two plasma rings are sum(GG) and sum(GG) respectively. rzlcs1 ) and sum(GG rzlcs2), where rzlcs represents the R and Z coordinates of the outermost closed magnetic surface corresponding to the plasma ring. Referring to the first double-ring configuration shown in Figure 2, sum(GG rzlcs1 ) can represent the current contained within the closed magnetic surface M11, sum(GG rzlcs2 The response matrix can be defined as sum(GG) representing the current contained within the closed magnetic surface M12. rzlcs1 ) must be equal to sum(GG rzlcs2 ).

[0061] Please continue referring to Figure 3. The second double-ring configuration includes two plasma rings located within a closed magnetic surface M20 (plasma rings in closed magnetic surfaces M21 and M22, respectively). The response feature set corresponding to the second double-ring configuration differs somewhat from the response feature sets shown in Figures 5 and 6; for example, the difference may lie only in the plasma magnetohydrodynamic equilibrium characteristics. The total current characteristics at each position in the response feature set corresponding to the second double-ring configuration include: the total current difference characteristics between the closed magnetic surface M20 and each position of the first plasma ring, the total current difference characteristics between the closed magnetic surface M20 and each position of the second plasma ring, the total current characteristics between the first plasma ring and each position of the target region, and the total current characteristics between the second plasma ring and each position of the target region. The target region is the area outside the first and second plasma rings within the closed magnetic surface M20; specifically, it is the region enclosed by the closed magnetic surface M20, excluding the areas enclosed by closed magnetic surfaces M21 and M22.

[0062] For example, rzlcs1 represents the region enclosed by the closed magnetic surface M20, rzlcs2 represents the region enclosed by the closed magnetic surface M21 where the first plasma ring is located, and rzlcs3 represents the region enclosed by the closed magnetic surface M22 where the second plasma ring is located. Figure 7 is a schematic diagram of another response matrix structure provided in an embodiment of this application. Figure 7 shows the response matrix corresponding to the second double-ring configuration. As shown in Figure 7, the response matrix uses sum(GG rzlcs1-3 The sum(GG) represents the total current difference characteristics between the closed magnetic surface M20 and various positions of the first plasma ring, expressed as sum(GG) rzlcs1-2 The sum(GG) represents the total current difference characteristics at various positions of the closed magnetic surface M20 and the second plasma ring, using the formula sum(GG) rzlcs2 +0.5GG rzlcs1-23 ) represents the total current characteristics at various locations in the first plasma ring and the target region, and uses sum(GG) to represent the total current characteristics at various locations in the target region. rzlcs3 +0.5GG rzlcs1-23 The value represents the total current characteristics at various locations in the second plasma ring and the target region.

[0063] sum(GG rzlcs1-3) can correspond to the current in the first remaining region after removing the region enclosed by closed magnetic surface M22 from the region enclosed by closed magnetic surface M20, sum(GG rzlcs1-2 This can correspond to the current in the second remaining region after removing the region enclosed by closed magnetic surface M21 from the region enclosed by closed magnetic surface M20. For this response matrix, the current contained in the first remaining region can be configured to be equal to the current contained in the second remaining region, i.e., sum(GG rzlcs1-3 =sum(GG) rzlcs1-2 sum(GG) rzlcs2 +0.5GG rzlcs1-23 The sum of the currents in the region enclosed by the closed magnetic surface M21 and the auxiliary region is given. This auxiliary region can be half the current in the region enclosed by the closed magnetic surface M20 after removing the regions enclosed by the closed magnetic surfaces M21 and M22. rzlcs3 +0.5GG rzlcs1-23 The sum of the currents within the enclosed region and auxiliary region of the closed magnetic surface M22 corresponds to this response matrix. The total plasma current can be configured to be the sum of the total currents contained within the enclosed region and auxiliary region of the closed magnetic surface M21 and the total currents contained within the enclosed region and auxiliary region of the closed magnetic surface M22.

[0064] In some implementations, referring to Figure 7, the response feature set corresponding to the second double-ring configuration includes the regularized constraint features polycoeffAeq1 and polycoeffAeq2 corresponding to the two plasmas, respectively, and the constraint matrix A of the safety factor at the magnetic axis corresponding to the two plasmas. q01 and A q02 In some embodiments, the plasma magnetohydrodynamic equilibrium characteristics in the response feature set corresponding to the second double-ring configuration may further include the pressure term P' and the poloidal current term FF' on the outermost closed magnetic surface of each plasma ring. For example, the pressure term P' on the outermost closed magnetic surface of the first plasma ring... rzlcs2 and polar current term FF' rzlcs2 The pressure term -P' on the outermost closed magnetic surface of the second plasma ring rzlcs3 And polar current term -FF' rzlcs3 .

[0065] In this embodiment, the plasma can be constrained in various ways based on the aforementioned response feature set, such as vertical displacement constraint, diamagnetic constraint, plasma current constraint, eddy current constraint, magnetic axis safety factor constraint, and magnetic surface topology constraint. Vertical displacement constraint facilitates the accurate identification of the plasma's vertical position that best matches the measurement signals of the magnetic flux loop and magnetic probe when the plasma changes rapidly in the vertical direction. Magnetic axis safety factor constraint can be used to control the shape of the current profile and actively introduce a hollow distribution during the startup phase. Diamagnetic constraint can be used to control the shape of the pressure profile; a very weak diamagnetic constraint can prevent the plasma from generating negative pressure. The information determination device determines the target state information within the reaction chamber based on this response feature set and performs inversion using real diamagnetic and eddy current information, thus ensuring good plasma equilibrium reconstruction and high accuracy of the determined target state information.

[0066] In this embodiment, the information determination device can determine the plasma current distribution based on the target configuration of the plasma at various moments during the nuclear fusion reaction, using the response matrix corresponding to the target configuration. This allows for the determination of the magnetic field and magnetic flux within the reaction chamber, thus obtaining the target state information within the reaction chamber. Furthermore, based on this target state information, magnetohydrodynamic (MHD) parameters such as poloidal specific pressure, pressure, and current profile can be calculated.

[0067] In some implementations, the information determination device may also have a display function or be connected to a display device. After obtaining the target state information within the reaction chamber, this target state information can be displayed graphically. The information determination device can display the target state information at various moments during the nuclear fusion reaction after the reaction has ended, or it can display the determined target state information in real time during the nuclear fusion reaction. For example, basic equilibrium information can be displayed, such as the inverted magnetic surface, pressure profile, current profile, and the evolution of equilibrium parameters such as large radius, small radius, and elongation ratio.

[0068] The method for determining the state information within the reaction chamber during a nuclear fusion reaction provided in this application provides corresponding response feature sets for the single-ring configuration, the first double-ring configuration, and the second double-ring configuration that change during the nuclear fusion reaction. Based on the diagnostic information of the nuclear fusion reactor, the target configuration corresponding to the current state of the reactor can be determined from among these multiple alternative configurations during the nuclear fusion reaction. The target configuration can be switched when the state changes. Balanced inversion processing is performed based on the response feature set corresponding to the target configuration to obtain the target state information within the current reaction chamber, that is, the plasma distribution information and the magnetic field distribution information. In this way, accurate determination of the corresponding state information within the reaction chamber can be achieved at each moment during the nuclear fusion reaction, reducing the limitations of determining the state information within the reaction chamber during the nuclear fusion reaction. This method has powerful configuration recognition capabilities and richer constraints. It can utilize diagnostic information to achieve full-process inversion calculation of the plasma in the nuclear fusion reactor from double-ring fusion to single-ring, obtaining the complex and variable evolution process of the plasma configuration and its related important physical quantities, providing effective feedback for the discharge operation of the nuclear fusion reactor.

[0069] In some embodiments, after determining the target state information within the reaction chamber at the current moment, the information determining device can adjust information such as the current applied to the corresponding components in the nuclear fusion reactor according to the subsequent needs of the nuclear fusion reaction. In some of these embodiments, the information determining device determines the diagnostic information that the diagnostic component should determine based on the target state information, compares this diagnostic information with the actual diagnostic information determined by the diagnostic component, can determine the diagnostic error of the detection component, and then adjust and correct the diagnostic component.

[0070] In some implementations, the information determining device in step 106 can iteratively perform multiple plasma equilibrium inversions to determine the target state information that meets the convergence conditions. The information determining device can perform plasma equilibrium inversion processing based on the Picard iterative method. The basic idea of ​​the Picard iterative method is to gradually linearize the nonlinear problem, approximating the true solution of the original problem through a series of iterative steps. Picard iteration utilizes external diagnostic information, using macroscopic physical parameters such as the total plasma current Ip and magnetic flux ψ to linearly represent the plasma current distribution using parameters, and calculates the results through equilibrium reconstruction iteration. The information determining device can be adjusted based on the traditional single-loop equilibrium inversion method ERST to achieve the equilibrium inversion processing in the embodiments of this application.

[0071] The core of the Picard iteration is the process of solving for free parameters using the response matrix, which establishes the relationship between the plasma current profile parameters to be determined and various diagnostics and constraints. The response matrix in the Picard iteration is not fixed but dynamically generated according to requirements for each calculation. For example, the number of columns in the response matrix depends on the unknown coefficients to be used, such as whether to consider eddies on the vacuum chamber wall and whether the eddies are Fourier series expanded, whether vertical displacement stabilization is performed, and whether the external coil current is fixed. The number of rows in the response matrix depends on the diagnostics or constraints to be used, which can also be assisted by adjusting the weights; for example, setting the weight to zero discards the current diagnostic or constraint. If new constraints or diagnostics need to be added later, the response matrix can be further refined.

[0072] In some embodiments, Figure 8 is a flowchart of a balance inversion process provided by an embodiment of this application. As shown in Figure 8, the balance inversion process in step 106 above, based on diagnostic information and the response feature set corresponding to the target configuration, determines the target state information in the reaction chamber, including steps s2 to s10, through which picard iteration can be realized.

[0073] Step s2: Based on the initial magnetic flux information corresponding to the target configuration, assign values ​​to each response feature in the response feature set corresponding to the target configuration.

[0074] Each reference configuration can be pre-configured with corresponding initial magnetic flux information, which serves as the start-up data for the equilibrium inversion process. For example, the initial magnetic flux information for a single-ring configuration includes the magnetic flux distribution information for one plasma ring, while the initial magnetic flux information for a double-ring configuration includes the magnetic flux distribution information for both plasma rings. The information determination device can input this initial magnetic flux information into the equilibrium inversion processing module to trigger the module to begin operation.

[0075] The information in the response feature set (i.e., the response matrix) consists entirely of features related to magnetic flux. Based on this magnetic flux, the corresponding feature values ​​can be determined. This is equivalent to assigning values ​​to each response feature in the response feature set based on the magnetic flux information, generating a response feature set with substantial content. Subsequently, an inversion process can be performed based on this response feature set to solve the problem.

[0076] Step s4: Perform balance inversion processing based on diagnostic information and the assigned response feature set to determine the system parameters of the nuclear fusion reactor, and determine the updated magnetic flux information based on the system parameters.

[0077] The information processing device can determine the system parameters θ by performing inversion processing based on the acquired real diagnostic information y and the assigned response feature set A(x) according to the aforementioned target formula y = A(x) × θ. In one embodiment, the information processing device can use Singular Value Decomposition (SVD) to solve the target formula to obtain the system parameters. The system parameters θ may include polynomial coefficients (such as poloidal current polynomial coefficients and pressure polynomial coefficients), eddy current Fourier coefficients, and vertical displacement information. The specific content included in the system parameters θ may be related to the response feature set, and may also include other information besides the aforementioned information, which is not limited here.

[0078] There is a defined relationship between the system parameters and the magnetic flux information, which can be characterized by formulas. After determining the system parameters, the information determining device can determine the corresponding magnetic flux information based on this relationship. In this embodiment, this magnetic flux information is referred to as updated magnetic flux information.

[0079] Step s6: Based on the updated magnetic flux information and the initial magnetic flux information, determine whether the convergence condition is met. If the convergence condition is not met, proceed to step s8; if the convergence condition is met, proceed to step s10.

[0080] For example, the convergence condition may include the difference between the updated magnetic flux information and the initial magnetic flux information being less than a certain threshold, such as |ψ(m)-ψ(m+1)|<ε. c Where ψ(m) represents the initial magnetic flux information, ψ(m+1) represents the updated magnetic flux information, and ε c This indicates the set convergence criterion. The information determining device can compare the updated magnetic flux information with the initial magnetic flux information to obtain a comparison result, and determine whether the convergence condition is met based on the comparison result.

[0081] Step s8: Determine the updated magnetic flux information as the initial magnetic flux information. Repeat step s2.

[0082] If the convergence condition is not met, the information determination device can perform another iterative equilibrium inversion, and re-execute step s2 and subsequent steps based on the updated magnetic flux information.

[0083] Step s10: Determine the target state information within the reaction chamber based on the initial magnetic flux information.

[0084] Once the convergence condition is met, the information determination device can stop the iterative process and determine the target state information within the reaction chamber based on the final updated magnetic flux information.

[0085] In this embodiment of the application, after the information determining device obtains the diagnostic information at a certain moment, it can execute steps s2 to s10 based on the diagnostic information. Based on the diagnostic information at a certain moment, multiple balance inversion iterations can be performed to determine the target state information corresponding to that moment.

[0086] Figure 9 is a simplified schematic diagram of a balance inversion process provided in an embodiment of this application, which corresponds to the process shown in Figure 8. As shown in Figure 9, the information determining device can sequentially execute the preparation process, the iteration process, and the post-processing process. The iteration process can be referred to the relevant descriptions of steps s2 to s8 above, and will not be repeated here.

[0087] In the preparation process, the information determination device reads the diagnostic information determined by the diagnostic components online, preprocesses the acquired diagnostic information, and converts it into a format suitable for analysis; alternatively, it can acquire locally stored diagnostic information. This diagnostic information may include plasma current information, eddy current information in the reaction chamber, and current information from the discharge coil. In the diagnostic information acquired by the information determination device (such as diagnostic information determined by the magnetic probe and flux loop), the eddy current information includes eddy currents induced by the external coil and eddy currents induced by internal ionization. The information determination device can choose to directly utilize the overall eddy current information for subsequent equilibrium inversion calculations (i.e., iterative processes), or it can choose to extract the response information of the external coil from the diagnostic information to calculate the eddy currents induced by the internal current or the external coil, and perform subsequent equilibrium inversion calculations based on this calculated eddy current. This eddy current information is used to determine the updated magnetic flux information in the iterative process.

[0088] In the post-processing flow, the information determination device can calculate pressure and current profile information based on the updated magnetic flux information obtained in the iterative process, and further calculate macroscopic MHD parameters such as poloidal specific pressure and internal inductance to generate a plasma equilibrium file. This equilibrium file includes target state information of the reaction chamber, such as information on current and magnetic flux within the reaction chamber, as well as geometrically relevant information about the plasma.

[0089] In some implementations, a weight can be set for each response feature in the response feature set as needed. Setting the weight to zero discards the response feature, ignoring it during calculation; a larger weight increases the impact of the response feature on the final result during calculation. Accordingly, step 106 above, which involves performing a balanced inversion process based on diagnostic information and the response feature set corresponding to the target configuration to determine the target state information within the reaction chamber, includes: performing a balanced inversion process based on diagnostic information, the response feature set corresponding to the target configuration, and the weights of each response feature in the response feature set, to obtain the target state information within the reaction chamber.

[0090] For example, the weights of each response feature in the response feature set can be pre-set by staff in a configuration file, such as based on plasma equilibrium inversion results from previous nuclear fusion reaction processes. The information determination device can acquire this configuration file and, during the equilibrium inversion process, combine the weights of each response feature in the configuration file with the actual content of the determined response features to perform calculations.

[0091] In some implementations, the weights of the response features can be automatically adjusted by the information determination device based on real-time data during the nuclear fusion reaction. In some implementations, after the nuclear fusion reaction, the weights of each response feature in the response feature set can be adjusted based on the actual situation during the nuclear fusion reaction to ensure better plasma equilibrium inversion in subsequent nuclear fusion reactions.

[0092] In one example, during a nuclear fusion reaction, images of the reaction chamber can be acquired using an image acquisition device (such as an altitude camera). An information determination device can determine reference state information within the reaction chamber based on the image information of the plasma acquired during the nuclear fusion reaction; it compares the target state information with the reference state information and adjusts the weights of each response feature in the response feature set based on the comparison results. This reference state information may include at least plasma morphology information. The information determination device can compare the plasma morphology in the target state information and the reference state information at various moments during the nuclear fusion reaction, and adjust the weights of the response features related to the plasma morphology in the response feature set based on the degree of similarity.

[0093] In another example, the weights of response features can be adjusted using diagnostic information. Accordingly, after performing a balance inversion process based on the diagnostic information and the response feature set corresponding to the target configuration in step 106 above to determine the target state information within the reaction chamber, the information determination device can determine the target diagnostic information corresponding to each diagnostic component of the nuclear fusion reactor based on the target state information; compare the actual diagnostic information of each diagnostic component with the target diagnostic information, and adjust the weights of each response feature in the response feature set based on the comparison results. This target diagnostic information may include probe signals, plasma currents, and eddy currents, among other things.

[0094] The information determination device can obtain some information that diagnostic components can diagnose by performing plasma equilibrium inversion. In this embodiment, this information is referred to as target diagnostic information. However, the target diagnostic information obtained by inversion may differ from the information actually diagnosed by the diagnostic components (e.g., referred to as actual diagnostic information). The information determination device can adjust the weights of the response features related to these diagnostic information based on the error between the target diagnostic information and the actual diagnostic information.

[0095] The following describes the implementation method of determining the target configuration from multiple alternative configurations of the plasma based on diagnostic information in step 104 above. In this embodiment, the magnetic flux extremum point (i.e., "O point") and the outermost closed magnetic surface of the plasma can be determined based on diagnostic information, and the target configuration can be determined based on this magnetic flux extremum point and the outermost closed magnetic surface. The magnetic flux at all positions around the magnetic flux extremum point is greater than or less than the magnetic flux at the magnetic flux extremum point, that is, a position where the magnetic flux is relatively large or small compared to the surrounding positions. Each plasma ring can correspond to a magnetic flux extremum point, which can be the center point of the plasma ring.

[0096] Step 104 above may include: determining the target magnetic flux extremum point of the plasma in the reaction chamber of the nuclear fusion reactor based on diagnostic information; determining the target outermost closed magnetic surface of the plasma based on the target magnetic flux extremum point; and determining the target configuration among various alternative configurations of the plasma based on the target magnetic flux extremum point and the target outermost closed magnetic surface. The magnetic flux extremum point mentioned below refers to the aforementioned magnetic flux extremum point. For example, based on diagnostic information, the information determining device can determine the location in the reaction chamber that satisfies the characteristics of the magnetic flux extremum point, and thus determine the target magnetic flux extremum point. Based on diagnostic information, the information determining device can determine all closed magnetic surfaces in the reaction chamber, and then determine the target outermost closed magnetic surface of the plasma among the closed magnetic surfaces surrounding the target magnetic flux extremum point.

[0097] For example, the information determination device can use a dichotomy method to locate the outermost closed magnetic surface of the plasma based on the location of the magnetic flux extremum and the coordinates of the inner wall of the reaction chamber. In some embodiments, the nuclear fusion reactor also includes a limiter. The limiter, also known as a gate, is installed inside the reaction chamber to confine the plasma boundary, preventing the plasma from contacting the reaction chamber wall and thus protecting the reaction chamber. In this configuration, the information determination device can locate the outermost closed magnetic surface of the target plasma based on the location of the magnetic flux extremum and the coordinates of the limiter.

[0098] In some implementations, the target magnetic flux extremum point may include all magnetic flux extremum points in the reaction chamber determined by the information determining device. However, due to the complexity of the various magnetic fields and current states in the reaction chamber, there may be some false magnetic flux extremum points that satisfy the characteristics of a magnetic flux extremum point but are not the center of the plasma ring. In this embodiment, these false magnetic flux extremum points need to be screened out from the determined magnetic flux extremum points to obtain the true target magnetic flux extremum point that can represent the plasma ring. For example, the black dot in the middle of each closed magnetic surface in Figures 2 to 4 can represent the target magnetic flux extremum point.

[0099] For example, by analyzing the positions of each determined magnetic flux extremum point, it can be determined whether each magnetic flux extremum point is a false magnetic flux extremum point. In this embodiment of the application, all positions that satisfy the characteristics of magnetic flux extremum points determined based on diagnostic information are referred to as candidate magnetic flux extremum points. Accordingly, the above-mentioned step of determining the target magnetic flux extremum point of the plasma in the reaction chamber of the nuclear fusion reactor based on diagnostic information includes: determining the candidate magnetic flux extremum points of the plasma in the reaction chamber of the nuclear fusion reactor based on diagnostic information; and screening out candidate magnetic flux extremum points that meet the screening conditions based on the positions of each candidate magnetic flux extremum point to determine the target magnetic flux extremum point. There can be multiple screening conditions. For example, if the true magnetic flux extremum point corresponding to the plasma ring cannot be located at or within certain positions, screening conditions can be directly set based on the position or region to directly screen out the candidate magnetic flux extremum points appearing at that position or region.

[0100] In a nuclear fusion reactor, a false magnetic flux extremum may appear in the region near the inner wall of the reactor chamber. To address this, screening conditions can be set, such as requiring the distance from the inner wall to be less than a distance threshold. This distance threshold can be 10 cm, 15 cm, or other values. Accordingly, the step of determining the target magnetic flux extremum by screening out candidate magnetic flux extremums that meet the screening conditions based on their locations includes: determining the distance between each candidate magnetic flux extremum and the inner wall of the reactor chamber based on their locations; screening out candidate magnetic flux extremums that meet the screening conditions to obtain a first auxiliary magnetic flux extremum; and determining the target magnetic flux extremum based on the first auxiliary magnetic flux extremum.

[0101] The information determining device can determine the distance between each candidate magnetic flux extremum point and the inner wall of the reaction chamber, and compare this distance with a distance threshold in the screening conditions to determine whether the candidate magnetic flux extremum point meets the screening conditions. Magnetic flux extremum points that meet the screening conditions are considered false magnetic flux extremum points and are thus screened out. In this embodiment, the candidate magnetic flux extremum points remaining after screening based on the distance threshold are all referred to as first auxiliary magnetic flux extremum points. In some cases, the first auxiliary magnetic flux extremum points can be directly determined as the target magnetic flux extremum points; in other cases, there may still be false magnetic flux extremum points among the first auxiliary magnetic flux extremum points, which need to be further screened out.

[0102] In a nuclear fusion reactor device that also includes a limiter, the information determination device can determine the distance between the candidate magnetic flux extremum point and the limiter, and then filter them out based on this distance and a distance threshold.

[0103] In nuclear fusion reactors, a spurious magnetic flux extremum may appear due to the influence of the MC coil current. In this case, a magnetic flux transition point is often present near the spurious extremum. At the magnetic flux transition point, magnetic field lines intersect and guide particles from one magnetic surface to another. Characteristics of the magnetic flux transition point include: in two mutually perpendicular directions (such as the R and Z directions of the reaction chamber), the magnetic flux in one direction is greater than the magnetic flux at the transition point itself, while the magnetic flux in the other direction is less than the magnetic flux at the transition point itself. Accordingly, screening criteria can be set based on the positional relationship between this magnetic flux transition point and the magnetic flux extremum. This magnetic flux transition point can also be referred to as the "X point".

[0104] In one implementation, since the distance between the spurious flux extrema and their accompanying flux transition points is small, the flux extrema can be filtered out based on this distance. In another implementation, the accompanying flux transition point of the spurious flux extrema will be located within a specific region, so the flux extrema can be filtered out based on the flux transition point and this region. In this embodiment, this region is referred to as the region to be analyzed. Accordingly, the above-mentioned step of screening out candidate magnetic flux extrema points that meet the screening criteria based on the location of each candidate magnetic flux extrema point, and determining the target magnetic flux extrema point, may include: determining the magnetic flux extrema point to be analyzed located in the region where the MC coil is located in the nuclear fusion reactor based on the location of each candidate magnetic flux extrema point; screening out the magnetic flux extrema points to be analyzed that meet the screening criteria among each candidate magnetic flux extrema point to obtain a second auxiliary magnetic flux extrema point; wherein, the screening criteria include having a magnetic flux transition point in the region to be analyzed, and the region to be analyzed includes the region where the MC coil is located; and determining the target magnetic flux extrema point based on the second auxiliary magnetic flux extrema point.

[0105] The region where the MC coil is located refers to the space occupied by the MC coil in the reaction chamber. The cross-section of the MC coil can be rectangular. From the longitudinal cross-section of the reaction chamber, the candidate magnetic flux extrema located within the region where the MC coil is located in the nuclear fusion reactor are situated within this rectangular region. For example, please continue to refer to Figure 4, where the two small squares in the reaction chamber 10 can represent the MC coil, and the area enclosed by these small squares can be considered the region where the MC coil is located. The information determination device can search for whether there are any candidate magnetic flux extrema located within the region where the MC coil is located based on the determined positions of the candidate magnetic flux extrema. In this embodiment, the candidate magnetic flux extrema located within the region where the MC coil is located are referred to as the magnetic flux extrema to be analyzed. For the magnetic flux extrema to be analyzed, it can be further determined whether it is a false magnetic flux extrema based on screening conditions.

[0106] The information determination device can determine the region to be analyzed based on the area where the MC coil is located. This region to be analyzed includes at least the area where the MC coil is located, and its area can be larger than the area where the MC coil is located. For example, the region to be analyzed can be obtained by proportionally enlarging the area where the MC coil is located, such as by four times, six times, or other factors. The center of this region to be analyzed can coincide with the center of the area where the MC coil is located. The information determination device can determine whether there is a magnetic flux transition point in the region to be analyzed corresponding to each magnetic flux extremum point to be analyzed, that is, whether there is a position that satisfies the characteristics of a magnetic flux transition point. If a magnetic flux transition point is determined to exist in the region to be analyzed, then the magnetic flux extremum point to be analyzed corresponding to that region is determined to be accompanied by a magnetic flux transition point. This magnetic flux extremum point to be analyzed meets the screening criteria and is considered a false magnetic flux extremum point, thus it can be screened out. After judging and screening the magnetic flux extremum points to be analyzed from the candidate magnetic flux extremum points in this way, the target magnetic flux extremum point can be determined based on the remaining candidate magnetic flux extremum points. In this embodiment of the application, the remaining candidate magnetic flux extremum point is referred to as the second auxiliary magnetic flux extremum point.

[0107] In some cases, the second auxiliary flux extremum point can be directly identified as the target flux extremum point; in other cases, false flux extremum points may exist among the second auxiliary flux extremum points, requiring further screening. In some implementations, the first auxiliary flux extremum point can be determined first using the aforementioned method, and then the flux extremum point to be analyzed can be determined from the first auxiliary flux extremum points. Further screening can then be performed based on screening conditions related to the region where the MC coil is located and the accompanying flux transition point to obtain the second auxiliary flux extremum point, thereby determining the target flux extremum point.

[0108] In some embodiments, the step of determining the target magnetic flux extremum point by screening out candidate magnetic flux extremum points that meet the screening criteria based on the location of each candidate magnetic flux extremum point includes: screening out candidate magnetic flux extremum points that meet the screening criteria based on the location of each candidate magnetic flux extremum point to obtain auxiliary magnetic flux extremum points; when the number of auxiliary magnetic flux extremum points is greater than 2, determining the auxiliary magnetic flux extremum point closest to the equatorial plane of the reaction chamber as the target magnetic flux extremum point; when the number of auxiliary magnetic flux extremum points is 2, determining the target magnetic flux extremum point based on the outermost closed magnetic surface corresponding to each of the two auxiliary magnetic flux extremum points, and the area of ​​the outermost closed magnetic surface corresponding to each auxiliary magnetic flux extremum point.

[0109] The process of eliminating candidate magnetic flux extrema that meet the elimination criteria can be achieved through any one or a combination of the two elimination methods mentioned above (one based on the distance from the inner wall of the reaction chamber, and the other based on the MC coil region and the magnetic flux transition point). The resulting auxiliary magnetic flux extrema can be either a first auxiliary magnetic flux extrema or a second auxiliary magnetic flux extrema. Alternatively, it can be achieved through other elimination methods different from the two methods mentioned above, which are not limited here.

[0110] Because in a nuclear fusion reactor with plasma ring fusion compression, the plasma sequentially changes from a first double-ring configuration to a second double-ring configuration, and then to a single-ring configuration during the nuclear fusion reaction, the maximum number of plasma rings in the reaction chamber should be two, and correspondingly, the maximum number of target magnetic flux extrema should be two. If, after the aforementioned screening, more than two auxiliary magnetic flux extrema are identified, then false magnetic flux extrema must exist among these auxiliary magnetic flux extrema, thus further screening of magnetic flux extrema is required.

[0111] In both the first and second double-ring configurations, the plasma stability is relatively high. After the aforementioned screening, only two magnetic flux extrema remain, and the probability of false magnetic flux extrema is low. However, in the initial stage of the fusion of two plasma rings into one, i.e., the initial stage of the transition from the second double-ring configuration to the single-ring configuration, the plasma stability is still relatively low. At this time, many small closed magnetic surfaces may be generated, resulting in multiple magnetic flux extrema. If the number of auxiliary magnetic flux extrema remaining after the aforementioned screening is greater than two, it is highly likely that this is the initial stage of the fusion of two plasma rings into one. At this time, the overall state in the reaction chamber is closer to the single-ring configuration, and it is more appropriate to determine a target magnetic flux extrema from these two auxiliary magnetic flux extrema. Since in the single-ring configuration, the plasma ring is located in the middle region of the reaction chamber, close to the equatorial plane of the reaction chamber, and the target magnetic flux extrema is located at the center of the plasma ring, the auxiliary magnetic flux extrema closest to the equatorial plane of the reaction chamber among these multiple auxiliary magnetic flux extrema can be determined as the target magnetic flux extrema.

[0112] In a nuclear fusion reactor with plasma ring fusion compression, the situation where two auxiliary magnetic flux extrema are obtained after the aforementioned screening of candidate magnetic flux extrema can include the following two scenarios. In the first scenario, the two plasma rings are in the process of approaching each other to fuse, and the plasma is in either a first or second double-ring configuration, with a small size difference between the two plasma rings. In this case, it is necessary to determine two target magnetic flux extrema, meaning both auxiliary magnetic flux extrema can be directly determined as target magnetic flux extrema. In the second scenario, the two plasma rings are in the initial stage of fusion into one plasma ring, i.e., the plasma is in the final stage of the second double-ring configuration or the initial stage of switching to a single-ring configuration. At this time, there will be two smaller plasma rings in the reaction chamber, with one plasma ring being much smaller than the other. The overall state of the reaction chamber is closer to a single-ring configuration, making it more appropriate to determine one target magnetic flux extrema from the two auxiliary magnetic flux extrema.

[0113] Since the scenario where two auxiliary flux extrema are obtained after the above screening of candidate flux extrema include both the first and second scenarios, and the target flux extrema required differs in each scenario, when the number of auxiliary flux extrema is two, the information determining device needs to determine which of the two scenarios is currently in order to determine the target flux extrema accordingly. Because the size relationship of the plasma rings differs between the two scenarios, the information determining device can make a judgment based on the size relationship of the plasma rings. The size of the plasma ring can be reflected by the area of ​​the region enclosed by its outermost closed magnetic surface. Therefore, the information determining device can screen the target flux extrema from the auxiliary flux extrema based on the area of ​​the region enclosed by the outermost closed magnetic surfaces corresponding to the two auxiliary flux extrema. The outermost closed magnetic surface corresponding to an auxiliary flux extrema is also the outermost closed magnetic surface surrounding that auxiliary flux extrema.

[0114] For example, the information determining device can determine the area percentage of each outermost closed magnetic surface within the two outermost closed magnetic surfaces based on the area of ​​the outermost closed magnetic surfaces corresponding to the two auxiliary flux extrema. This area percentage is equal to the area of ​​the region enclosed by one outermost closed magnetic surface divided by the sum of the areas of the regions enclosed by each of the two outermost closed magnetic surfaces. The area percentage of any outermost closed magnetic surface within the two outermost closed magnetic surfaces will be referred to simply as the area percentage of the outermost closed magnetic surface. Since one plasma ring is smaller in the second case, a smaller target ratio can be set, and the area percentage of each outermost closed magnetic surface can be compared with this target ratio. If the area percentage of the outermost closed magnetic surface is less than the target ratio, the plasma ring with the smaller area corresponding to the outermost closed magnetic surface is determined, and the outermost closed magnetic surface and its corresponding auxiliary flux extrema can be discarded, while the other auxiliary flux extrema is determined as the target flux extrema. For example, the target ratio can be 5%, 10%, or other values.

[0115] In this embodiment, when two auxiliary magnetic flux extrema are obtained after the aforementioned screening of candidate magnetic flux extrema, the outermost closed magnetic surfaces corresponding to these two auxiliary magnetic flux extrema can be different (e.g., when the plasma is in a first double-ring configuration) or the same (e.g., when the plasma is in a second double-ring configuration). The specific process by which the information determining device determines the target magnetic flux extrema can differ depending on these two possible cases regarding the outermost closed magnetic surfaces. When the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extrema are the same, it is impossible to directly determine the two plasma rings based on these outermost closed magnetic surfaces; therefore, further analysis is required to determine the target magnetic flux extrema. However, when the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extrema are different, the target magnetic flux extrema can be directly determined based on these outermost closed magnetic surfaces.

[0116] When two auxiliary flux extrema correspond to two different outermost closed magnetic surfaces, the information determining device can directly determine the area ratio of the outermost closed magnetic surface corresponding to each auxiliary flux extrema and compare this area ratio with a target ratio. If the area ratio of one outermost closed magnetic surface is less than the target ratio, the auxiliary flux extrema corresponding to that outermost closed magnetic surface is discarded, and the other auxiliary flux extrema is determined as the target flux extrema. If the area ratios of both outermost closed magnetic surfaces are not less than the target ratio, both auxiliary flux extrema can be determined as target flux extrema. Accordingly, the step of determining the target magnetic flux extremum point based on the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extremum points and the area of ​​the outermost closed magnetic surfaces corresponding to each auxiliary magnetic flux extremum point may include: when the two auxiliary magnetic flux extremum points correspond to two different outermost closed magnetic surfaces, and the area ratio of one of the two outermost closed magnetic surfaces in the two outermost closed magnetic surfaces is less than the target ratio, the auxiliary magnetic flux extremum point corresponding to the other outermost closed magnetic surface is determined as the target magnetic flux extremum point; when the two auxiliary magnetic flux extremum points correspond to two different outermost closed magnetic surfaces, and the area ratio of each outermost closed magnetic surface in the two outermost closed magnetic surfaces is not less than the target ratio, both of the auxiliary magnetic flux extremum points are determined as target magnetic flux extremum points.

[0117] When two auxiliary magnetic flux extrema correspond to two different outermost closed magnetic surfaces, the information determination device can determine the outermost closed magnetic surface (such as the auxiliary outermost closed magnetic surface) that does not surround the other auxiliary magnetic flux extrema for each of the two auxiliary magnetic flux extrema, and then determine the target magnetic flux extrema based on the area ratio of the auxiliary outermost closed magnetic surface. The steps described above for determining the target magnetic flux extremum point based on the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extremum points and the area of ​​the outermost closed magnetic surfaces corresponding to each auxiliary magnetic flux extremum point may include: when the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extremum points are the same, determining the auxiliary outermost closed magnetic surface corresponding to each auxiliary magnetic flux extremum point that does not surround the other auxiliary magnetic flux extremum point, thus obtaining two auxiliary outermost closed magnetic surfaces; when the area ratio of one auxiliary outermost closed magnetic surface in the two auxiliary outermost closed magnetic surfaces is less than the target ratio, determining the auxiliary magnetic flux extremum point corresponding to the other outermost closed magnetic surface as the target magnetic flux extremum point; when the area ratio of each auxiliary outermost closed magnetic surface in the two auxiliary outermost closed magnetic surfaces is not less than the target ratio, determining both auxiliary magnetic flux extremum points as target magnetic flux extremum points.

[0118] For example, referring to Figure 3, the outermost closed magnetic surface directly determined for both auxiliary flux extrema can be M20. Further, the information determining device determines an outermost closed magnetic surface M21 that does not surround the lower auxiliary flux extrema for the upper auxiliary flux extrema; and an outermost closed magnetic surface M22 that does not surround the upper auxiliary flux extrema for the lower auxiliary flux extrema. The information determining device also determines the area ratio of the outermost closed magnetic surface M21 and the area ratio of the outermost closed magnetic surface M22, and compares these area ratios with a target ratio, determining the target flux extrema based on the comparison result. The area ratio of the outermost closed magnetic surface M21 is S21 / (S21+S22), where S21 represents the area of ​​the region enclosed by the outermost closed magnetic surface M21, and S22 represents the area of ​​the region enclosed by the outermost closed magnetic surface M22.

[0119] After determining the target magnetic flux extremum point through the above method, the information determining device can determine the target outermost closed magnetic surface of the plasma based on the target magnetic flux extremum point. The required target outermost closed magnetic surface differs for different target magnetic flux extremum points. For example, if there is only one target magnetic flux extremum point, or if there are two target magnetic flux extremum points corresponding to different outermost closed magnetic surfaces, the outermost closed magnetic surface corresponding to the target magnetic flux extremum point is directly determined as the target outermost closed magnetic surface of the plasma. As another example, if there are two target magnetic flux extremum points, and the outermost closed magnetic surfaces corresponding to the two target magnetic flux extremum points are the same, this outermost closed magnetic surface is determined as the first target outermost closed magnetic surface of the plasma. For each of the two target magnetic flux extremum points, an outermost closed magnetic surface that does not surround the other target magnetic flux extremum point is determined, resulting in the second and third target outermost closed magnetic surfaces of the plasma. Thus, when the number of target magnetic flux extrema is 1, one target outermost closed magnetic surface can be determined; when the number of target magnetic flux extrema is 2 and they correspond to different outermost closed magnetic surfaces, two target outermost closed magnetic surfaces can be determined; when the number of target magnetic flux extrema is 2 and the outermost closed magnetic surfaces corresponding to the two target magnetic flux extrema are the same, three target outermost closed magnetic surfaces can be determined.

[0120] In this embodiment, the processes of determining the target magnetic flux extremum point and the target outermost closed magnetic surface can be performed simultaneously. During the determination of the target magnetic flux extremum point, the process of determining the outermost closed magnetic surface is also performed. After determining the target magnetic flux extremum point, the information determining device can determine the target outermost closed magnetic surface based on the previously determined outermost closed magnetic surface. For example, in the case where two auxiliary magnetic flux extremum points are determined after screening, the information determining device can determine the second target closed magnetic surface and the third target outermost closed magnetic surface based on the outermost closed magnetic surface determined for each auxiliary magnetic flux extremum point that does not surround the other auxiliary magnetic flux extremum point. In some embodiments, the information determining device can also re-determine the target outermost closed magnetic surface based on the target magnetic flux extremum point after determining the target magnetic flux extremum point; this is not limited here.

[0121] After determining the target magnetic flux extremum point and the target outermost closed magnetic surface, the information determining device can determine the target configuration from multiple candidate configurations of the plasma based on the target magnetic flux extremum point and the target outermost closed magnetic surface. For example, the target configuration can be determined based on the number of target magnetic flux extremum points and the number of target outermost closed magnetic surfaces. When the number of target magnetic flux extremum points is 1 and the number of target outermost closed magnetic surfaces is 1, the single-loop configuration among the multiple candidate configurations of the plasma is determined as the target configuration; when the number of target magnetic flux extremum points is 2 and the number of target outermost closed magnetic surfaces is 2, the first double-loop configuration among the multiple candidate configurations of the plasma is determined as the target configuration; when the number of target magnetic flux extremum points is 2 and the number of target outermost closed magnetic surfaces is 3, the second double-loop configuration among the multiple candidate configurations of the plasma is determined as the target configuration.

[0122] Figure 10 is a simplified flowchart of determining a target configuration according to an embodiment of this application. As shown in Figure 10, the information determining device can analyze the information of auxiliary flux extrema points (Opoint in the figure) obtained after filtering. Based on this flux extrema point information, for any auxiliary flux extrema point, such as Opoint(1,;), its outermost closed magnetic surface LCFS1 can be found, and the coordinate information rzlcs1 of the outermost closed magnetic surface in the set coordinate system can be determined. In the figure, imc represents the configuration switching command, corresponding to the target configuration. imc=0 represents a single-loop configuration, imc=1 represents a second double-loop configuration, and imc=2 represents a first double-loop configuration. When only Opoint(1,;) is found, imc can be assumed to be 0 based on the current information. Then, the analysis can continue based on the information of the auxiliary flux extrema points to determine whether there are two auxiliary flux extrema points. If there are no two auxiliary flux extrema, the coordinates of the outermost closed magnetic surface of the final target can be directly determined as rzlcs = rzlcs1, and the configuration switching command corresponding to the final target configuration is imc = 0. This then outputs the final results for the target flux extrema and the outermost closed magnetic surface. If there are two auxiliary flux extrema, further analysis can be performed.

[0123] If an auxiliary flux extremum point Opoint(2,;) is determined, its outermost closed magnetic surface LCFS2 is also located for this auxiliary flux extremum point, and the coordinate information rzlcs2 of the outermost closed magnetic surface in the set coordinate system is determined. Based on the current information (i.e., two flux extremum points and two outermost closed magnetic surfaces), imc can be assumed to be 2. Then, the precise target configuration can be further determined. The information determination device can determine whether the two outermost closed magnetic surfaces LCFS1 and LCFS2 corresponding to the two auxiliary flux extremum points coincide. If they do not coincide, it is further determined whether there are false flux extremum points among the two auxiliary flux extremum points, such as by judging the ratio ε of the area ratio of the outermost closed magnetic surface to the target.

[0124] As shown in Figure 10, the area (S) of each outermost closed magnetic surface can be determined. LCFS1 or S LCFS2 Is it less than ε and the sum of the areas of the two outermost closed magnetic surfaces, S? LCFS1+2The product of the two auxiliary magnetic flux extrema is used. When the area of ​​each outermost closed magnetic surface is not less than the product, the two auxiliary magnetic flux extrema are determined as the target magnetic flux extrema, and the two outermost closed magnetic surfaces are determined as the target outermost closed magnetic surfaces of the plasma. The target configuration is the first double-ring configuration, and the coordinate information of the target outermost closed magnetic surface is determined accordingly: rzlcs = (rzlcs1, rzlcs2), imc = 2. When the area of ​​one outermost closed magnetic surface is not less than the product, the outermost closed magnetic surface with the larger area can be determined as the target outermost closed magnetic surface of the plasma, and the other outermost closed magnetic surface and the corresponding auxiliary magnetic flux extrema are discarded. The target configuration is the single-ring configuration, and the coordinate information of the target outermost closed magnetic surface is determined accordingly: rzlcs = maxsize(LCFS1, 2), imc = 0.

[0125] When the outermost closed magnetic surfaces LCFS1 and LCFS2 coincide, the aforementioned rzlcs1 = rzlcs2 can be represented solely by rzlcs1, and the two outermost closed magnetic surfaces can also be represented solely by LCFS1. For each auxiliary flux extremum point, find the auxiliary outermost closed magnetic surface that does not contain the other auxiliary flux extremum point. In the figure, limit(Opoint(i,;)) indicates that the magnetic surface does not enclose Opoint(i,;). For example, for Opoint(1,;), the auxiliary outermost closed magnetic surface LCFS3 is found, and its coordinate information is represented by rzlcs2; for Opoint(2,;), the auxiliary outermost closed magnetic surface LCFS4 is found, and its coordinate information is represented by rzlcs3. Then, it can be further determined whether there are false flux extremum points among the two auxiliary flux extremum points, such as by judging the ratio ε of the area of ​​the outermost closed magnetic surface to the target. The area (S) of each outermost closed magnetic surface can be determined. LCFS33 or S LCFS4 Is it less than ε and the sum of the areas of the two outermost closed magnetic surfaces, S? LCFS3+4 The product of.

[0126] When the area of ​​each outermost closed magnetic surface is not less than the product, both auxiliary magnetic flux extrema are determined as target magnetic flux extrema. The outermost closed magnetic surfaces LCFS1, LCFS3, and LCFS4 are determined as the target outermost closed magnetic surfaces of the plasma and the internal separation line. The target configuration is the second double-ring configuration. Accordingly, the coordinate information of the target outermost closed magnetic surface is determined as rzlcs = (rzlcs1, rzlcs2, rzlcs3), imc = 1. When the area of ​​one outermost closed magnetic surface is not less than the product, the outermost closed magnetic surface with the larger area can be determined as the target outermost closed magnetic surface of the plasma. The other outermost closed magnetic surface and the corresponding auxiliary magnetic flux extrema are discarded. The target configuration is the single-ring configuration. Accordingly, the coordinate information of the target outermost closed magnetic surface is determined as rzlcs = maxsize(LCFS1, 3, 4), imc = 0.

[0127] After determining the target configuration of the plasma in the aforementioned manner, the information determination device can acquire the response feature set corresponding to the target configuration and perform plasma equilibrium inversion to determine the target state information in the reaction chamber.

[0128] The method for determining state information provided in this application embodiment can be applied to SUNIST or SUNIST-2 nuclear fusion reactors, and also to other nuclear fusion reactors that meet corresponding conditions (such as the plasma configuration including any of the aforementioned alternative configurations). The plasma equilibrium inversion in this application embodiment mainly employs numerical methods for calculation, such as the Picard iteration method. This application embodiment can accurately locate the target magnetic flux extrema and the outermost closed magnetic surface of the plasma, possessing a powerful ability to determine the plasma configuration based on the magnetic axis (corresponding to the magnetic flux extrema) and the number of closed magnetic surfaces. During calculation, it can accurately identify the plasma configuration and switch between different configurations, achieving a complete inversion of the plasma process from double-ring fusion to single-ring fusion.

[0129] In this embodiment, more constraints are set for plasma equilibrium inversion, such as constraints on eddy currents, vertical displacement stability, diamagnetics, safety factors at the magnetic axis, and weights, which can improve the inversion effect. This embodiment adopts the dynamic generation mode of the response matrix in the ERST method and adds a total eddy current constraint. Combined with the measured diamagnetic flux, the probe signal can be normally calibrated to achieve more accurate equilibrium calculation. For the first double-ring configuration, a constraint is added that the plasma current contained in the outermost closed magnetic surface of the upper and lower rings is equal, and the weight of this constraint can be adjusted according to the actual situation. For the second double-ring configuration, constraints are added that the pressure distribution and poloidal current distribution on the outermost closed magnetic surface of the upper and lower rings are equal, as well as a total current constraint. Furthermore, the weights of the corresponding constraints can be adjusted through a configuration file based on the degree of agreement between the plasma morphology in the high-speed camera and the inversion results, as well as the errors between the inverted and measured probe signals, plasma currents, eddy currents, etc.

[0130] In summary, the method for determining the state information within the reaction chamber during a nuclear fusion reaction provided in this application provides corresponding response feature sets for the single-ring configuration, the first double-ring configuration, and the second double-ring configuration that change during the nuclear fusion reaction. Based on the diagnostic information of the nuclear fusion reactor during the nuclear fusion reaction, the target configuration corresponding to the current state of the nuclear fusion reactor can be determined from among these multiple alternative configurations. Then, based on the response feature set corresponding to the target configuration, equilibrium inversion processing can be performed to obtain the target state information within the current reaction chamber, that is, the plasma distribution information and the magnetic field distribution information. In this way, accurate determination of the corresponding state information within the reaction chamber can be achieved at each moment during the nuclear fusion reaction process, reducing the limitations of determining the state information within the reaction chamber during the nuclear fusion reaction.

[0131] Corresponding to the above method embodiments, this application also provides an embodiment of a device for determining the state information inside the reaction chamber during a nuclear fusion reaction. Figure 11 is a schematic diagram of the structure of a device for determining the state information inside the reaction chamber during a nuclear fusion reaction provided in this application embodiment. As shown in Figure 11, the determining device includes:

[0132] The acquisition module 1102 is used to acquire diagnostic information of the nuclear fusion reactor during the nuclear fusion reaction process;

[0133] The first determining module 1104 is used to determine the target configuration among a variety of alternative configurations of plasma based on diagnostic information; wherein the variety of alternative configurations includes a single-ring configuration, a first double-ring configuration, and a second double-ring configuration, the first double-ring configuration containing two independent plasma rings, and the second double-ring configuration containing two plasma rings located in a closed magnetic surface.

[0134] The second determining module 1106 is used to perform equilibrium inversion processing based on diagnostic information and the response feature set corresponding to the target configuration to determine the target state information in the reaction chamber; wherein, the response feature set includes multiple response features reflecting the relationship between diagnostic information and state information, and the target state information includes the distribution information of plasma and the distribution information of magnetic field in the reaction chamber.

[0135] In some implementations, the first determining module 1104 includes:

[0136] The first determination submodule is used to determine the target magnetic flux extremum point of the plasma in the reaction chamber of the nuclear fusion reactor based on diagnostic information; wherein the magnetic flux at each position around the magnetic flux extremum point is greater than or less than the magnetic flux at the magnetic flux extremum point.

[0137] The second determination submodule is used to determine the outermost closed magnetic surface of the plasma based on the target magnetic flux extremum point;

[0138] The third determination submodule is used to determine the target configuration from multiple alternative configurations of the plasma based on the target magnetic flux extremum point and the target outermost closed magnetic surface.

[0139] In some implementations, the first determining submodule includes:

[0140] The determination unit is used to determine the candidate magnetic flux extrema of the plasma in the reaction chamber of a nuclear fusion reactor based on diagnostic information.

[0141] The screening unit is used to screen out candidate magnetic flux extrema points that meet the screening conditions based on the position of each candidate magnetic flux extrema point, and to determine the target magnetic flux extrema point.

[0142] In some embodiments, the screening unit is used to: determine the distance between each candidate magnetic flux extremum point and the inner wall of the reaction chamber in the nuclear fusion reactor based on the location of each candidate magnetic flux extremum point; screen out candidate magnetic flux extremum points that meet the screening conditions from among the candidate magnetic flux extremum points to obtain a first auxiliary magnetic flux extremum point; wherein the screening conditions include the distance to the inner wall of the reaction chamber being less than a distance threshold; and determine a target magnetic flux extremum point based on the first auxiliary magnetic flux extremum point.

[0143] In some embodiments, the screening unit is used to: determine, based on the location of each candidate magnetic flux extremum point, the magnetic flux extremum point to be analyzed located within the region where the fusion compression MC coil is located in the nuclear fusion reactor; screen out the magnetic flux extremum points to be analyzed that meet the screening criteria from among the candidate magnetic flux extremum points to obtain a second auxiliary magnetic flux extremum point; wherein, the screening criteria include having a magnetic flux transition point in the region to be analyzed, the region to be analyzed including the region where the MC coil is located; in two mutually perpendicular directions, the magnetic flux in one direction where the magnetic flux transition point is located is greater than the magnetic flux at the magnetic flux transition point, and the magnetic flux in the other direction is less than the magnetic flux at the magnetic flux transition point; and determine the target magnetic flux extremum point based on the second auxiliary magnetic flux extremum point.

[0144] In some implementations, the screening unit is used to: screen out candidate magnetic flux extrema that meet the screening conditions based on the position of each candidate magnetic flux extrema, to obtain auxiliary magnetic flux extrema; when the number of auxiliary magnetic flux extrema is greater than 2, determine the auxiliary magnetic flux extrema closest to the equatorial plane of the reaction chamber as the target magnetic flux extrema; when the number of auxiliary magnetic flux extrema is 2, determine the target magnetic flux extrema based on the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extrema, and the area of ​​the outermost closed magnetic surface corresponding to each auxiliary magnetic flux extrema.

[0145] In some implementations, the screening unit is used to: determine the auxiliary magnetic flux extreme point corresponding to the other outermost closed magnetic surface as the target magnetic flux extreme point when the two auxiliary magnetic flux extreme points correspond to two different outermost closed magnetic surfaces, and the area ratio of one outermost closed magnetic surface in the two outermost closed magnetic surfaces is less than the target ratio; and determine both auxiliary magnetic flux extreme points as target magnetic flux extreme points when the two auxiliary magnetic flux extreme points correspond to two different outermost closed magnetic surfaces, and the area ratio of each outermost closed magnetic surface in the two outermost closed magnetic surfaces is not less than the target ratio.

[0146] In some implementations, the screening unit is used for:

[0147] When the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extrema are the same, determine the auxiliary outermost closed magnetic surface that does not surround the other auxiliary magnetic flux extrema corresponding to each auxiliary magnetic flux extrema, and obtain the two auxiliary outermost closed magnetic surfaces.

[0148] If the area ratio of one auxiliary outermost closed magnetic surface to the other auxiliary outermost closed magnetic surface is less than the target ratio, the auxiliary magnetic flux extreme point corresponding to the other outermost closed magnetic surface is determined as the target magnetic flux extreme point.

[0149] If the area ratio of each auxiliary outermost closed magnetic surface in the two auxiliary outermost closed magnetic surfaces is not less than the target ratio, then both auxiliary magnetic flux extrema points are determined as target magnetic flux extrema points.

[0150] In some implementations, the second determining submodule is used for:

[0151] When the number of target magnetic flux extreme points is 1, or when the number of target magnetic flux extreme points is 2 and they correspond to different outermost closed magnetic surfaces, the outermost closed magnetic surface corresponding to the target magnetic flux extreme point is determined as the target outermost closed magnetic surface of the plasma.

[0152] When the number of target magnetic flux extrema is 2, and the outermost closed magnetic surfaces corresponding to the two target magnetic flux extrema are the same, the outermost closed magnetic surface is determined as the first target outermost closed magnetic surface of the plasma.

[0153] For each of the two target magnetic flux extrema, the outermost closed magnetic surface that does not surround the other target magnetic flux extrema is determined, thus obtaining the second target outermost closed magnetic surface and the third target outermost closed magnetic surface of the plasma.

[0154] In some implementations, the third determining submodule is used for:

[0155] When the number of target magnetic flux extrema is 1 and the number of target outermost closed magnetic surfaces is 1, the single-loop configuration among the various alternative configurations of the plasma is determined as the target configuration.

[0156] When the number of target magnetic flux extrema is 2 and the number of target outermost closed magnetic surfaces is 2, the first double-ring configuration among the various alternative configurations of the plasma is determined as the target configuration.

[0157] When the number of target magnetic flux extrema is 2 and the number of target outermost closed magnetic surfaces is 3, the second double-ring configuration among the various alternative configurations of the plasma is determined as the target configuration.

[0158] In some embodiments, the response feature sets corresponding to the various alternative configurations all include: plasma magnetohydrodynamic equilibrium features, eddy current features of the reaction chamber, vertical displacement features of the plasma, and discharge coil features; the plasma magnetohydrodynamic equilibrium features include the pressure features and poloidal current features of the plasma ring, the total current features at each position of the plasma ring, regularization constraint features, contramagnetic constraint features, constraint features of the safety factor at the magnetic axis, the influence features of the fixed boundary on the plasma, and topological features;

[0159] The total current characteristics of each position of the plasma ring corresponding to the first double-ring configuration include: the total current characteristics of each position of the two plasma rings;

[0160] The total current characteristics of each position of the plasma ring corresponding to the second double-ring configuration include: the total current difference characteristics between the closed magnetic surface and each position of the first plasma ring, the total current difference characteristics between the closed magnetic surface and each position of the second plasma ring, the total current characteristics between the first plasma ring and each position of the target region, and the total current characteristics between the second plasma ring and each position of the target region; wherein, the target region is the region outside the first plasma ring and the second plasma ring in the closed magnetic surface.

[0161] In some implementations, the second determining module 1106 is used to: perform a balance inversion process based on diagnostic information, combined with the response feature set corresponding to the target configuration and the weights of each response feature in the response feature set, to obtain the target state information in the reaction chamber.

[0162] In some embodiments, the determining device further includes:

[0163] The third determination module is used to determine the reference state information inside the reaction chamber by using image information collected from the plasma inside the reaction chamber during the nuclear fusion reaction process.

[0164] The first adjustment module is used to compare the target state information and the reference state information, and adjust the weight of each response feature in the response feature set based on the comparison results.

[0165] In some embodiments, the determining device further includes:

[0166] The fourth determination module is used to perform equilibrium inversion processing based on diagnostic information and the response feature set corresponding to the target configuration. After determining the target state information in the reaction chamber, it determines the target diagnostic information corresponding to each diagnostic component of the nuclear fusion reactor based on the target state information.

[0167] The second adjustment module is used to compare the actual diagnostic information of each diagnostic component with the target diagnostic information, and adjust the weight of each response feature in the response feature set based on the comparison results.

[0168] In some implementations, the second determining module 1106 is used to:

[0169] Based on the initial magnetic flux information corresponding to the target configuration, values ​​are assigned to each response feature in the response feature set corresponding to the target configuration;

[0170] Based on the diagnostic information and the assigned response feature set, a balance inversion process is performed to determine the system parameters of the nuclear fusion reactor, and the updated magnetic flux information is determined based on the system parameters.

[0171] Based on the updated magnetic flux information and the initial magnetic flux information, if the convergence condition is not met, the updated magnetic flux information is determined as the initial magnetic flux information, and the process of assigning values ​​to each response feature in the response feature set corresponding to the target configuration and subsequent steps is repeated based on the initial magnetic flux information corresponding to the target configuration until the convergence condition is met. The target state information in the reaction chamber is then determined based on the updated magnetic flux information.

[0172] In summary, the device for determining the state information within the reaction chamber during a nuclear fusion reaction provided in this application embodiment has corresponding response feature sets for the single-ring configuration, the first double-ring configuration, and the second double-ring configuration that change during the nuclear fusion reaction. Based on the diagnostic information of the nuclear fusion reactor during the nuclear fusion reaction, the target configuration corresponding to the current state of the nuclear fusion reactor can be determined from among these multiple alternative configurations. Then, based on the response feature set corresponding to the target configuration, equilibrium inversion processing can be performed to obtain the target state information within the current reaction chamber, that is, the plasma distribution information and the magnetic field distribution information. In this way, accurate determination of the corresponding state information within the reaction chamber can be achieved at each moment during the nuclear fusion reaction process, reducing the limitations of determining the state information within the reaction chamber during the nuclear fusion reaction.

[0173] The various embodiments in this application are described in a progressive manner. Similar or identical parts between embodiments can be referred to mutually. Each embodiment focuses on describing the differences from other embodiments. For the secure two-party inference device based on fully homomorphic encryption, relevant details can be found in the description of the embodiment on the method for determining the state information inside the reaction chamber during a nuclear fusion reaction.

[0174] Figure 12 is a structural block diagram of a computing device provided in an embodiment of this application. The components of the computing device 1200 include, but are not limited to, a memory 1210 and a processor 1220. The processor 1220 is connected to the memory 1210 via a bus 1230, and a database 1250 is used to store data.

[0175] The computing device 1200 also includes an access device 1240, which enables the computing device 1200 to communicate via one or more networks 1260. Examples of such networks include Public Switched Telephone Network (PSTN), Local Area Network (LAN), Wide Area Network (WAN), Personal Area Network (PAN), or combinations of communication networks such as the Internet. The access device 1240 may include one or more of any type of wired or wireless network interface (e.g., a network interface controller (NIC)), such as an IEEE 802.11 Wireless Local Area Network (WLAN) wireless interface, a Wi-MAX (Worldwide Interoperability for Microwave Access) interface, an Ethernet interface, a Universal Serial Bus (USB) interface, a cellular network interface, a Bluetooth interface, or a Near Field Communication (NFC) interface.

[0176] In one embodiment of this application, the aforementioned components of the computing device 1200, as well as other components not shown in FIG12, may be interconnected, for example, via a bus. It should be understood that the computing device block diagram shown in FIG12 is merely for illustrative purposes and is not intended to limit the scope of this application. Those skilled in the art can add or replace other components as needed.

[0177] The computing device 1200 can be any type of stationary or mobile computing device, including mobile computers or mobile computing devices (e.g., tablet computers, personal digital assistants, laptop computers, notebook computers, netbooks, etc.), mobile phones (e.g., smartphones), wearable computing devices (e.g., smartwatches, smart glasses, etc.) or other types of mobile devices, or stationary computing devices such as desktop computers or personal computers (PCs). The computing device 1200 can also be a mobile or stationary server.

[0178] The processor 1220 is used to execute computer programs / instructions, which, when executed by the processor, implement the steps in the above-described method, as shown in any of Figures 1 and 8 to 10.

[0179] As the computing device embodiment is basically similar to the method embodiment for determining the state information in the reaction chamber during a nuclear fusion reaction, the description is relatively simple, and relevant parts can be found in the description of the method embodiment.

[0180] One embodiment of this application also provides a computer-readable storage medium storing computer instructions that, when executed by a processor, implement the steps of the method for determining the state information within a reaction chamber during a nuclear fusion reaction. The computer instructions include computer program code, which may be in the form of source code, object code, executable file, or some intermediate form. The computer-readable storage medium may include any entity or device capable of carrying the computer program code, a recording medium, a USB flash drive, a portable hard drive, a magnetic disk, an optical disk, a computer memory, a read-only memory (ROM), a random access memory (RAM), an electrical carrier signal, a telecommunication signal, and a software distribution medium, etc. It should be noted that the content included in the computer-readable storage medium may be appropriately added or removed according to the requirements of legislation and patent practice in the jurisdiction. For example, in some jurisdictions, according to legislation and patent practice, the computer-readable storage medium may not include electrical carrier signals and telecommunication signals.

[0181] One embodiment of this application also provides a computer program product, including a computer program / instructions that, when executed in a processor, implement the steps of the method for determining the state information inside the reaction chamber during the nuclear fusion reaction process described above.

[0182] For the computer-readable storage medium embodiment and the computer program product embodiment, since they are basically similar to the method embodiment for determining the state information in the reaction chamber during a nuclear fusion reaction, the description is relatively simple. For relevant details, please refer to the description of the method embodiment for determining the state information in the reaction chamber during a nuclear fusion reaction.

[0183] The foregoing has described specific embodiments of this application. Other embodiments are within the scope of the appended claims. In some cases, the actions or steps recited in the claims may be performed in a different order than that shown in the embodiments and may still achieve the desired results. Furthermore, the processes depicted in the drawings do not necessarily require the specific or sequential order shown to achieve the desired results. In some embodiments, multitasking and parallel processing are also possible or may be advantageous.

[0184] Those skilled in the art should also understand that the embodiments described in the specification are all preferred embodiments, and the actions and modules involved are not necessarily essential to this application. In the above embodiments, the descriptions of each embodiment have different focuses, and for parts not described in detail in a certain embodiment, please refer to the relevant descriptions of other embodiments.

[0185] The preferred embodiments disclosed above are merely illustrative of this application. The optional embodiments do not exhaustively describe all details, nor do they limit this application to the specific implementations described. Clearly, many modifications and variations can be made based on the content of this application. These embodiments are selected and specifically described in this application to better explain the principles and practical applications of this application, thereby enabling those skilled in the art to better understand and utilize this application.

Claims

1. A method for determining the state information within a reaction chamber during a nuclear fusion reaction, comprising: To obtain diagnostic information of the nuclear fusion reactor during the nuclear fusion process; Based on the diagnostic information, a target configuration is determined from a variety of alternative plasma configurations, wherein the variety of alternative configurations includes a single-ring configuration, a first double-ring configuration, and a second double-ring configuration, wherein the first double-ring configuration comprises two independent plasma rings, and the second double-ring configuration comprises two plasma rings located in a closed magnetic surface; and Based on the diagnostic information and the response feature set corresponding to the target configuration, a balance inversion process is performed to determine the target state information within the reaction chamber. The response feature set includes multiple response features that reflect the relationship between the diagnostic information and the state information. The target state information includes the distribution information of plasma and the distribution information of magnetic field in the reaction chamber.

2. The method according to claim 1, wherein, The step of determining the target configuration from multiple alternative configurations of the plasma based on the diagnostic information includes: Based on the diagnostic information, the target magnetic flux extreme point of the plasma in the reaction chamber of the nuclear fusion reactor is determined, wherein the magnetic flux at each position around the magnetic flux extreme point is greater than or less than the magnetic flux at the magnetic flux extreme point. Based on the target magnetic flux extremum point, determine the outermost closed magnetic surface of the plasma; and Based on the target magnetic flux extremum point and the target outermost closed magnetic surface, the target configuration is determined from a variety of alternative configurations of the plasma.

3. The method according to claim 2, wherein, The step of determining the target magnetic flux extremum point of the plasma in the reaction chamber of the nuclear fusion reactor based on the diagnostic information includes: Based on the diagnostic information, candidate magnetic flux extrema points of the plasma in the reaction chamber of the nuclear fusion reactor are determined; and Based on the location of each candidate magnetic flux extremum point, candidate magnetic flux extremum points that meet the screening criteria are eliminated, and the target magnetic flux extremum point is determined.

4. The method according to claim 3, wherein, The process of eliminating candidate magnetic flux extrema points that meet the elimination criteria based on the location of each candidate magnetic flux extrema point, and determining the target magnetic flux extrema point, includes: Based on the positions of each candidate magnetic flux extremum point, the distance between each candidate magnetic flux extremum point and the inner wall of the reaction chamber in the nuclear fusion reactor is determined; candidate magnetic flux extremum points that meet the screening criteria are eliminated from the candidate magnetic flux extremum points to obtain a first auxiliary magnetic flux extremum point, wherein the screening criteria include the distance to the inner wall of the reaction chamber being less than a distance threshold; a target magnetic flux extremum point is determined based on the first auxiliary magnetic flux extremum point; and / or, Based on the location of each candidate magnetic flux extremum point, the magnetic flux extremum point to be analyzed is determined within the region where the fusion compression MC coil is located in the nuclear fusion reactor. Among the candidate magnetic flux extremum points, those meeting the screening criteria are eliminated to obtain a second auxiliary magnetic flux extremum point. Based on the second auxiliary magnetic flux extremum point, a target magnetic flux extremum point is determined. The screening criteria include having a magnetic flux transition point in the region to be analyzed, the region to be analyzed including the region where the MC coil is located, and in two mutually perpendicular directions, the magnetic flux in one direction around the magnetic flux transition point is greater than the magnetic flux at the magnetic flux transition point, and the magnetic flux in the other direction is less than the magnetic flux at the magnetic flux transition point.

5. The method according to claim 3 or 4, wherein, The process of eliminating candidate magnetic flux extrema points that meet the elimination criteria based on the location of each candidate magnetic flux extrema point, and determining the target magnetic flux extrema point, includes: Based on the location of each candidate magnetic flux extremum point, candidate magnetic flux extremum points that meet the screening conditions are eliminated to obtain auxiliary magnetic flux extremum points. When the number of auxiliary magnetic flux extrema is greater than 2, the auxiliary magnetic flux extrema closest to the mid-plane of the reaction chamber is determined as the target magnetic flux extrema; and When the number of auxiliary magnetic flux extrema is 2, the target magnetic flux extrema is determined based on the outermost closed magnetic surface corresponding to the two auxiliary magnetic flux extrema and the area of ​​the outermost closed magnetic surface corresponding to each auxiliary magnetic flux extrema.

6. The method according to claim 5, wherein, The determination of the target magnetic flux extremum point based on the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extremum points, and the area of ​​the outermost closed magnetic surface corresponding to each auxiliary magnetic flux extremum point, includes: When the two auxiliary magnetic flux extrema points correspond to two different outermost closed magnetic surfaces, and the area ratio of one outermost closed magnetic surface in the two outermost closed magnetic surfaces is less than the target ratio, the auxiliary magnetic flux extrema point corresponding to the other outermost closed magnetic surface is determined as the target magnetic flux extrema point. When the two auxiliary magnetic flux extreme points correspond to two different outermost closed magnetic surfaces, and the area ratio of each outermost closed magnetic surface in the two outermost closed magnetic surfaces is not less than the target ratio, the two auxiliary magnetic flux extreme points are determined as target magnetic flux extreme points. When the outermost closed magnetic surfaces corresponding to the two auxiliary magnetic flux extrema points are the same, determine the auxiliary outermost closed magnetic surface that does not surround the other auxiliary magnetic flux extrema point corresponding to each auxiliary magnetic flux extrema point, and obtain two auxiliary outermost closed magnetic surfaces. If the area ratio of one auxiliary outermost closed magnetic surface to the other of the two auxiliary outermost closed magnetic surfaces is less than the target ratio, then the auxiliary magnetic flux extremum point corresponding to the other outermost closed magnetic surface is determined as the target magnetic flux extremum point; and If the area ratio of each auxiliary outermost closed magnetic surface in the two auxiliary outermost closed magnetic surfaces is not less than the target ratio, then both auxiliary magnetic flux extrema points are determined as target magnetic flux extrema points.

7. The method according to any one of claims 2 to 4, wherein, The determination of the outermost closed magnetic surface of the plasma based on the target magnetic flux extremum point includes: When the number of target magnetic flux extreme points is 1, or when the number of target magnetic flux extreme points is 2 and they correspond to different outermost closed magnetic surfaces, the outermost closed magnetic surface corresponding to the target magnetic flux extreme point is determined as the target outermost closed magnetic surface of the plasma. When the number of target magnetic flux extrema is 2, and the outermost closed magnetic surfaces corresponding to the two target magnetic flux extrema are the same, the outermost closed magnetic surface is determined as the first target outermost closed magnetic surface of the plasma; and For each of the two target magnetic flux extrema points, the outermost closed magnetic surface that does not surround the other target magnetic flux extrema point is determined, thus obtaining the second target outermost closed magnetic surface and the third target outermost closed magnetic surface of the plasma.

8. The method according to any one of claims 2 to 4, wherein, The determination of the target configuration from multiple alternative configurations of the plasma based on the target magnetic flux extremum point and the target outermost closed magnetic surface includes: When the number of target magnetic flux extrema is 1 and the number of target outermost closed magnetic surfaces is 1, the single-loop configuration among the various alternative configurations of the plasma is determined as the target configuration. When the number of target magnetic flux extrema is 2 and the number of target outermost closed magnetic surfaces is 2, the first double-ring configuration among the various alternative configurations of the plasma is determined as the target configuration; and When the number of target magnetic flux extrema is 2 and the number of target outermost closed magnetic surfaces is 3, the second double-ring configuration among the various alternative configurations of the plasma is determined as the target configuration.

9. The method according to any one of claims 1 to 4, wherein, The response feature sets corresponding to the various alternative configurations all include: plasma magnetohydrodynamic equilibrium features, eddy current features of the reaction chamber, vertical displacement features of the plasma, and discharge coil features. The plasma magnetohydrodynamic equilibrium characteristics include: pressure characteristics and poloidal current characteristics of the plasma ring, total current characteristics at various locations of the plasma ring, regularization constraint characteristics, contramagnetic constraint characteristics, constraint characteristics of the safety factor at the magnetic axis, influence characteristics of the fixed boundary on the plasma, and topological characteristics. The total current characteristics of each position of the plasma ring corresponding to the first double-ring configuration include: the total current characteristics of each position of the two plasma rings; The total current characteristics of each position of the plasma ring corresponding to the second double-ring configuration include: the total current difference characteristics between the closed magnetic surface and each position of the first plasma ring, the total current difference characteristics between the closed magnetic surface and each position of the second plasma ring, the total current characteristics between the first plasma ring and each position of the target region, and the total current characteristics between the second plasma ring and each position of the target region, wherein the target region is the region outside the first plasma ring and the second plasma ring in the closed magnetic surface.

10. The method according to any one of claims 1 to 4, wherein, The step of performing a balance inversion process based on the diagnostic information and the response feature set corresponding to the target configuration to determine the target state information within the reaction chamber includes: Based on the diagnostic information, combined with the response feature set corresponding to the target configuration and the weights of each response feature in the response feature set, a balance inversion process is performed to obtain the target state information in the reaction chamber.

11. The method of claim 10, further comprising: The reference state information of the reaction chamber is determined by collecting image information of the plasma in the reaction chamber during the nuclear fusion reaction. The target state information and the reference state information are compared, and the weights of each response feature in the response feature set are adjusted based on the comparison results. And / or, After performing a balanced inversion process based on the diagnostic information and the response feature set corresponding to the target configuration to determine the target state information in the reaction chamber, the target diagnostic information corresponding to each diagnostic component of the nuclear fusion reactor is determined based on the target state information; the actual diagnostic information of each diagnostic component is compared with the target diagnostic information, and the weight of each response feature in the response feature set is adjusted based on the comparison result.

12. The method according to any one of claims 1 to 4, wherein, The step of performing a balance inversion process based on the diagnostic information and the response feature set corresponding to the target configuration to determine the target state information within the reaction chamber includes: Based on the initial magnetic flux information corresponding to the target configuration, values ​​are assigned to each response feature in the response feature set corresponding to the target configuration; Based on the diagnostic information and the assigned response feature set, a balance inversion process is performed to determine the system parameters of the nuclear fusion reactor, and the updated magnetic flux information is determined based on the system parameters; and Based on the updated magnetic flux information and the initial magnetic flux information, if the convergence condition is met, the updated magnetic flux information is determined as the initial magnetic flux information, and the steps of assigning values ​​to each response feature in the response feature set corresponding to the target configuration and subsequent steps are re-executed based on the initial magnetic flux information corresponding to the target configuration until the convergence condition is met. Based on the updated magnetic flux information, the target state information in the reaction chamber is determined.

13. A device for determining the state information within a reaction chamber during a nuclear fusion reaction, comprising: The acquisition module is configured to acquire diagnostic information of the nuclear fusion reactor during the nuclear fusion reaction process; A first determining module is configured to determine a target configuration from a plurality of candidate configurations of the plasma based on the diagnostic information, wherein the plurality of candidate configurations include a single-ring configuration, a first double-ring configuration, and a second double-ring configuration, the first double-ring configuration comprising two independent plasma rings, and the second double-ring configuration comprising two plasma rings located in a closed magnetic surface; and The second determining module is configured to perform a balance inversion process based on the diagnostic information and the response feature set corresponding to the target configuration to determine the target state information in the reaction chamber. The response feature set includes multiple response features that reflect the relationship between the diagnostic information and the state information. The target state information includes the distribution information of plasma and the distribution information of magnetic field in the reaction chamber.

14. A computing device, comprising: Memory, configured to store computer programs / instructions; and A processor is configured to execute the computer program / instructions, which, when executed by the processor, implement the method according to any one of claims 1 to 12.

15. A computer-readable storage medium storing a computer program / instructions that, when executed by a processor, implement the method of any one of claims 1 to 12.

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