Magnetic confinement fusion plasma temperature diagnostic method, apparatus and device

Abstract

The application relates to a magnetic confinement fusion plasma temperature diagnosis method, device and equipment, wherein the method comprises the following steps: establishing a neutron yield database, including a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; collecting ion density and total neutron yield of external experimental equipment; assuming that only beam-target reaction exists in an initial stage, obtaining an initial temperature estimation value based on the ion density and the total neutron yield; obtaining first neutron yield and second neutron yield based on the initial temperature estimation value and the ion density, and obtaining theoretical total neutron yield; comparing the difference between the total neutron yield and the theoretical total neutron yield until convergence, obtaining the temperature estimation value as the plasma temperature; and outputting a diagnosis result as an initial temperature of the next moment to realize time sequence evolution analysis. The scheme fully utilizes the thermonuclear fusion and beam-target reaction database, effectively distinguishes the contributions of the two types of reactions to the neutron yield, and avoids the limitations of a traditional single reaction model.

Description

Technical Field

[0001] This invention relates to the field of ion temperature diagnosis for magnetic confinement fusion devices, and more particularly to a method, apparatus, and equipment for diagnosing the temperature of magnetic confinement fusion plasma. Background Technology

[0002] In magnetic confinement fusion research, ion temperature, as a core parameter for satisfying the Lawson criterion and regulating reaction rate and confinement performance, presents a critical challenge for the operation of tokamak devices. This parameter not only directly affects whether the fusion reaction can proceed stably and continuously, but is also closely related to the overall performance and energy production efficiency of the device.

[0003] The behavior of plasma in magnetic confinement fusion is complex and variable. As a core physical parameter characterizing plasma energy distribution, the spatial distribution characteristics of ion temperature are crucial, directly affecting the duration of energy confinement and the power density of the fusion reaction. Different temperature distribution characteristics may lead to significant differences in energy confinement efficiency and energy dissipation behavior.

[0004] Currently, the main detection methods include electron cyclotron radiation measurement and Thomson scattering diagnostics, which can achieve multi-regional and multi-temporal scale measurements of plasma ion and electron temperatures. However, these existing techniques still have significant limitations. For example, X-ray diagnostic methods rely on a measurement window, leading to window occupancy, and low-energy X-rays cannot penetrate the blanket. Neutron yield-based thermometry methods are only applicable to thermonuclear reaction-dominated scenarios, severely limiting their universality. Laser-induced fluorescence-based methods can only measure boundary plasmas, leaving the central region's plasma temperature unmeasurable, greatly limiting their application prospects. Summary of the Invention

[0005] The technical problem to be solved by the present invention is to provide a method, apparatus and equipment for temperature diagnosis of magnetic confinement fusion plasma.

[0006] To achieve the above-mentioned objective, this invention provides a method for diagnosing the temperature of magnetically confined fusion plasma, comprising the following steps: S1. Establish a neutron yield database, wherein the neutron yield database includes: a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; S2. Collect the ion density from external experimental equipment. Total neutron production ; S3. Assuming that the initial stage of the magnetic confinement fusion reaction in the external experimental device only involves beam-target reaction, and based on ion density... Total neutron production The initial temperature estimate was obtained by querying the neutron yield database of the beam-target reaction. ; S4. Based on the initial temperature estimate and ion density Query the neutron yield database and obtain the first neutron yield. Second neutron production And obtain the theoretical total neutron yield. Among them, the theoretical total neutron yield for ; S5. Comparison of total neutron production With theoretical total neutron yield ,like Then lower the initial temperature estimate. Conversely, if Then increase the initial temperature estimate. Among them, adjusting the initial temperature estimate value downwards / increasing upwards. Then, update the initial temperature estimate using either the bisection method or the gradient descent method. To temperature estimate And, based on the updated temperature estimates Repeat steps S4 to S5 until... The time convergence yields the estimated temperature value at that moment. As the plasma temperature, where... The preset threshold; S6. Output the obtained plasma temperature as the diagnostic result at the current moment, and use it as the initial temperature at the next moment. Repeat steps S4 to S6 to achieve temporal evolution analysis of plasma temperature.

[0007] According to one aspect of the present invention, step S1, the step of establishing a neutron yield database, includes: S11. Based on the ENDF database, temperature correction is carried out on the cross section of the deuterium-deuterium fusion reaction under non-equilibrium conditions in order to establish a multi-temperature fusion differential cross section database applicable to non-equilibrium plasma; S12. The thermonuclear fusion neutron yield under different combinations of ion density and temperature is calculated using the parametric method to construct the thermonuclear fusion neutron yield database; S13. Using the classical stopping power model, calculate the slowing time and slowing energy spectrum of deuterium ions in plasma under different temperature conditions, and calculate the target neutron yield based on the multi-temperature fusion differential cross section database and the slowing energy spectrum to construct the target reaction neutron yield database.

[0008] According to one aspect of the present invention, in step S11, the step of performing temperature correction on the deuterium-deuterium fusion reaction cross section under non-equilibrium state based on the ENDF database, the ENDF / B-VII database and the velocity grouping method are used to perform temperature correction on the deuterium-deuterium fusion reaction cross section that occurs during the slowing process of deuterium plasma with deuterium ions incident at a specific temperature.

[0009] According to one aspect of the present invention, step S11, which involves performing temperature correction on the deuterium-deuterium fusion reaction cross section under non-equilibrium conditions based on the ENDF database to establish a multi-temperature fusion differential cross section database suitable for non-equilibrium plasmas, includes: S111. Assuming the target particle deuterium is in thermal equilibrium, its velocity follows a Maxwell distribution with isotropic velocity direction. The initial energy of the input incident particle deuterium is... The initial temperature of the target particle deuterium ; S112. Discretize the target particle deuterium velocity magnitude and polar angle into groups, and calculate the velocity magnitude weights for each group. and polar angle weight ; S113. Select the target deuterium particle and the incident deuterium particle from a certain group after grouping, and calculate the relative velocity between the target deuterium particle and the incident deuterium particle. and relative energy ; S114. Based on the relative energy The microscopic reaction cross section between an incident deuterium particle of a given energy and a target deuterium particle of a certain energy group is obtained by interpolation in the ENDF / B-VII database. ; S115. Repeat steps S111 to S114 to obtain the velocity magnitude and direction of the target particle deuterium for all energy groups, and perform a weighted summation on all grouping results to obtain the temperature-corrected microscopic reaction cross section. To establish a multi-temperature fusion differential cross section database applicable to non-equilibrium plasmas.

[0010] According to one aspect of the present invention, in step S112, the target particle velocity magnitude and polar angle of the target particle deuterium are discretized by grouping, and the velocity magnitude weight of each group is calculated respectively. and polar angle weight In the steps, the speed magnitude weight Represented as: ; ; in, Indicates speed The ratio of particles below, i.e., velocity The probability of the number of particles falling out of the total number of particles. This represents the velocity of the deuterium particle. Indicates the mass of a deuterium particle. Represents the Boltzmann constant. Indicates the initial temperature of the target particle deuterium; The polar angle weight Represented as: ; in, Represents solid angle, This represents the polar angle, i.e., the velocity of the target particle deuterium. y The included angle of the axis; In step S113, target deuterium particles and incident deuterium particles from a certain group after grouping are selected, and the relative velocities of the target deuterium particles and incident deuterium particles are calculated. and relative energy In the steps, the relative energy Represented as: ; in, Indicates the mass of a deuterium particle. This represents the relative velocity between the target particle deuterium and the incident particle deuterium; In step S115, steps S111 to S114 are repeated to obtain the velocity magnitude and direction of the target particle deuterium for all energy groups. The results of all groupings are then weighted and summed to obtain the temperature-corrected microscopic reaction cross section. In the steps, the temperature-corrected microscopic reaction cross section Represented as: ; in, Indicates speed The speed magnitude weights are as follows: Indicates speed Polar angle weights, subscripts , This represents a number of a two-dimensional matrix.

[0011] According to one aspect of the present invention, in step S12, the step of calculating the thermonuclear fusion neutron yield under different combinations of ion density and temperature using a parametric method to construct the thermonuclear fusion neutron yield database, involves constructing the thermonuclear fusion reaction rate based on the parametric method. Formula, and based on the thermonuclear fusion reaction rate The formula yields temperatures ranging from 0.5 keV to 10 keV, with a deuterium ion density of... Thermonuclear fusion neutron yield database; The thermonuclear fusion reaction rate The formula is expressed as: ; ; ; ; ; ; ; in, This represents the volume of the plasma configuration mesh. This represents the initial energy in the energy cluster. This represents the energy after deuterium slowing down. Indicates the density of deuterium ions. The average thermonuclear reaction rate is a function of temperature, indicated by the subscript. , This represents an index of a two-dimensional matrix. Indicates the reaction cross section. , , The three-dimensional coordinates representing the plasma configuration. Indicates the small horizontal radius of the plasma. This represents the angle between the line connecting a point on the magnetic surface to the origin and the horizontal axis. Indicates the circumferential angle, used to describe the position of the plasma in the circumferential direction. This represents the largest radius of the final closed magnetic field. The triangular deformation of plasma, that is, the degree to which the plasma cross-section deviates from a circle, is represented. This represents the small radius of the final closed magnetic field. Expressed as the elongation ratio of the plasma, This indicates the correction of the temperature parameter. Represents energy parameters, This represents the mass of the incident deuterium particle. Represents the speed of light. This represents the Gamow barrier parameter. Indicates the Shavlanov offset. , , , , , and All are constants.

[0012] According to one aspect of the present invention, in step S13, the slowing time and slowing energy spectrum of deuterium ions in plasma under different temperature conditions are calculated using a classical stopping power model, and the target neutron yield is calculated based on the multi-temperature fusion differential cross section database and the slowing energy spectrum to construct the target reaction neutron yield database. In this step, the target reaction rate is constructed based on the multi-temperature fusion differential cross section database and the slowing energy spectrum. The formula yields a neutral beam power of 4 MW at incident particle energies of 75 keV, 70 keV, 60 keV, 50 keV, 40 keV, 30 keV, and 20 keV, at temperatures ranging from 0.5 keV to 10 keV, with a deuterium ion density of [missing value]. Database of neutron yields in beam-target reactions; The beam target reaction rate The formula is expressed as: ; ; in, This represents the macroscopic reaction cross section of the deuterium-deuterium fusion reaction. For the slowing process of deuterium ions from the first Energy group slowed down to the first The flux of an energy group, which is physically defined as the average track length of a particle within its volume of motion per unit time. Indicates volume, This represents the sum of the trajectories of all particles within that volume.

[0013] According to one aspect of the invention, it further includes: S7. Set a time step to repeat steps S1 to S6 within the time step to obtain the plasma temperature within the current time step, and output the plasma temperature obtained within the current time step as the diagnostic result of the current time step, and use it as the initial temperature of the next time step to complete the temporal evolution analysis of the plasma temperature over the entire time period.

[0014] To achieve the above-mentioned objective, the present invention provides a magnetic confinement fusion plasma temperature diagnostic device, comprising: A database module is used to establish a neutron yield database, wherein the neutron yield database includes: a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; The external data acquisition module is used to collect the ion density of external experimental equipment. Total neutron production ; The iterative module is used to assume that only beam-target reactions exist in the initial stage of the magnetic confinement fusion reaction in the external experimental device, and is based on ion density. Total neutron production The initial temperature estimate was obtained by querying the neutron yield database of the beam-target reaction. ; and, based on the initial temperature estimate and ion density Query the neutron yield database and obtain the first neutron yield. Second neutron production And obtain the theoretical total neutron yield. Among them, the theoretical total neutron yield ; and, compare total neutron production With theoretical total neutron yield ,like Then lower the initial temperature estimate. Conversely, if Then increase the initial temperature estimate. Among them, adjusting the initial temperature estimate value downwards / increasing upwards. Then, update the initial temperature estimate using either the bisection method or the gradient descent method. To temperature estimate And, based on the updated temperature estimates Regaining the theoretical total neutron yield until The time convergence yields the estimated temperature value at that moment. As the plasma temperature, where... The preset threshold; Furthermore, the obtained plasma temperature is output as the diagnostic result at the current moment and used as the initial temperature at the next moment to achieve temporal evolution analysis of plasma temperature.

[0015] To achieve the above-mentioned objectives, the present invention provides a device comprising at least one processor, at least one memory, and a data bus; The processor and the memory communicate with each other via the data bus; The memory stores program instructions that can be executed by the processor, which invokes the program instructions to execute the aforementioned magnetic confinement fusion plasma temperature diagnostic method.

[0016] According to one aspect of the present invention, this scheme fully utilizes thermonuclear fusion and beam-target reaction databases. Through a multi-physics model, it can effectively distinguish the contributions of two types of reactions to neutron yield, avoiding the limitations of traditional single-reaction models in temperature inversion. The algorithm, through dynamic iterative correction, can adapt to changes in reaction mechanisms during experiments, improving the accuracy and reliability of temperature diagnosis.

[0017] According to one aspect of the present invention, this approach is not only applicable to magnetic confinement fusion devices such as tokamaks, but can also be extended to other fusion experimental platforms with multiple neutron production mechanisms.

[0018] According to one aspect of the present invention, this aspect obtains a database of neutron yields at a fixed power for different ion densities and temperatures based on the formulas for beam-target reaction rate and thermonuclear fusion reaction rate.

[0019] According to one aspect of the present invention, the iterative calculation method of this approach completely eliminates the drawback of relying on traditional measurement windows for ion temperature diagnosis.

[0020] According to one aspect of the present invention, based on the latest cross-sectional data and related physical models from the ENDF database, the differential reaction cross-section of the deuterium-deuterium fusion reaction is temperature-corrected, creating a multi-temperature cross-section database suitable for magnetic confinement fusion. This significantly improves the accuracy of subsequent neutron yield simulation calculations. This database covers a wide temperature range and accurately corrects the reaction cross-sections at each temperature node, effectively solving the applicability problem of traditional databases under high-temperature fusion conditions. Attached Figure Description

[0021] Figure 1 This is a flowchart illustrating the steps of a magnetic confinement fusion plasma temperature diagnostic method according to one embodiment of the present invention. Figure 2 A flowchart of a magnetic confinement fusion plasma temperature diagnosis method according to one embodiment of the present invention; Figure 3 This is a schematic diagram of the relative velocities between the incident particle and the target particle according to one embodiment of the present invention. Figure 4 This is a schematic diagram of the discretization processing of the thermal motion velocity of target particles according to one embodiment of the present invention. Figure 5 This is a diagram showing the plasma configuration mesh generation result of one embodiment of the present invention; Figure 6 This is a simulation result diagram of the thermonuclear fusion reaction rate according to one embodiment of the present invention; Figure 7 This is a graph showing the results of calculating the ion temperature using the bisection iterative method in one embodiment of the present invention, wherein... Figure 7 (a) shows the output change curve during the iteration process. Figure 7 (b) shows the temperature change curve during the iteration process; Figure 8 This is a graph showing the results of gradient descent iterative calculation of ion temperature in one embodiment of the present invention, wherein... Figure 8(a) shows the output change curve during the iteration process. Figure 8 (b) shows the temperature change curve during the iteration process. Detailed Implementation

[0022] The present invention will now be described in detail with reference to the accompanying drawings and specific embodiments. The embodiments cannot be described in detail here, but the embodiments of the present invention are not limited to the following embodiments.

[0023] Combination Figure 1 and Figure 2 As shown, according to one embodiment of the present invention, a method for diagnosing the temperature of magnetic confinement fusion plasma includes the following steps: S1. Establish a neutron yield database, which includes: a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; S2. Collect the ion density from external experimental equipment. Total neutron production ; S3. Assuming that the initial stage of the magnetic confinement fusion reaction in the external experimental device only involves beam-target reaction, and based on ion density... Total neutron production The initial temperature estimate was obtained by querying the beam-target reaction neutron yield database. ; S4. Based on the initial temperature estimate and ion density Query the neutron yield database and obtain the first neutron yield. Second neutron production And obtain the theoretical total neutron yield. Among them, the theoretical total neutron yield ; S5. Comparison of total neutron production With theoretical total neutron yield ,like Then lower the initial temperature estimate. Conversely, if Then increase the initial temperature estimate. Among them, adjusting the initial temperature estimate downwards / upwards. When needed, update the initial temperature estimate using either the bisection method or the gradient descent method. To temperature estimate And, based on the updated temperature estimates Repeat steps S4 to S5 until... The time convergence yields the estimated temperature value at that moment. As the plasma temperature, where... The preset threshold; S6. Output the obtained plasma temperature as the diagnostic result at the current moment, and use it as the initial temperature at the next moment. Repeat steps S4 to S6 to achieve temporal evolution analysis of plasma temperature.

[0024] According to one embodiment of the present invention, step S1, the step of establishing a neutron yield database, includes: S11. Based on the ENDF database, temperature correction is carried out on the cross section of the deuterium-deuterium fusion reaction under non-equilibrium conditions in order to establish a multi-temperature fusion differential cross section database applicable to non-equilibrium plasma; S12. The parametric method was used to calculate the neutron yield of thermonuclear fusion under different combinations of ion density and temperature, so as to construct a database of thermonuclear fusion neutron yield; S13. Using the classical stopping power model, the slowing time and slowing energy spectrum of deuterium ions in plasma under different temperature conditions are calculated, and the target neutron yield is calculated based on the multi-temperature fusion differential cross section database and the slowing energy spectrum to construct a target reaction neutron yield database.

[0025] According to one embodiment of the present invention, in step S11, the step of performing temperature correction on the deuterium-deuterium fusion reaction cross section under non-equilibrium conditions based on the ENDF database involves using the ENDF / B-VII database and combining it with the velocity grouping method to perform temperature correction on the deuterium-deuterium fusion reaction cross section occurring during the slowing process of deuterium plasma incident at a specific temperature by deuterium ions. Specifically, the reaction cross section data provided by the ENDF / B-VII database are all based on a laboratory frame of reference. The database provides microscopic reaction cross sections (including absorption and scattering cross sections) of particles with various energies incident on "stationary" target particles. However, since this data system uses a laboratory frame of reference and assumes that the target particles are "stationary," while in the experiment, the target particles are always in a state of intense thermal motion. Therefore, the microscopic reaction cross section data cannot be directly used in the simulation process, and temperature correction of the cross section is required first.

[0026] In this embodiment, step S11, which involves performing temperature correction on the deuterium-deuterium fusion reaction cross section under non-equilibrium conditions based on the ENDF database to establish a multi-temperature fusion differential cross section database suitable for non-equilibrium plasmas, includes: S111. Assuming the target particle deuterium is in thermal equilibrium, its velocity follows a Maxwell distribution with isotropic velocity direction. The initial energy of the input incident particle deuterium is... The initial temperature of the target particle deuterium ; S112. Discretize the target particle deuterium velocity magnitude and polar angle by grouping them, and calculate the velocity magnitude weights for each group. and polar angle weight The obtained weights are used to correct the uncorrected microscopic reaction cross section, thus forming a corrected microscopic reaction cross section; specifically, the velocity magnitude weights... Represented as: ; ; in, Indicates speed The ratio of particles below, i.e., velocity The probability of the number of particles falling out of the total number of particles. This represents the velocity of the deuterium particle. Indicates the mass of a deuterium particle. Represents the Boltzmann constant. This indicates the initial temperature of the target particle deuterium (also known as the target nucleus deuterium); Polar angle weight Represented as: ; in, Represents solid angle, This represents the polar angle, i.e., the velocity of the target particle deuterium. The included angle of the axis.

[0027] S113. Select the target deuterium particle and the incident deuterium particle from a certain group after grouping, and calculate the relative velocity between the target deuterium particle and the incident deuterium particle. and relative energy In this embodiment, relative energy Represented as: ; in, Indicates the mass of a deuterium particle. This represents the relative velocity between the target particle deuterium and the incident particle deuterium; S114. Based on relative energy The microscopic reaction cross section between a deuterium particle of a given energy and a deuterium target particle of a certain energy group is obtained by interpolation search in the ENDF / B-VII database. ; S115. Repeat steps S111 to S114 to obtain the velocity magnitude and direction of the target particle deuterium for all energy groups, and perform a weighted summation on all grouping results to obtain the temperature-corrected microscopic reaction cross section. To establish a multi-temperature fusion differential cross-section database applicable to non-equilibrium plasmas; among which, the temperature-corrected microscopic reaction cross-sections... Represented as: ; in, Indicates speed The speed magnitude weights are as follows: Indicates speed Polar angle weights, subscripts , This represents a number for a two-dimensional matrix, which is constructed based on the incident energy and temperature.

[0028] To further illustrate this scheme, the temperature correction process in step S11 will be described in more detail.

[0029] In this embodiment, the ENDF database provides energy at 100 Up to dozens The data describes the microscopic reaction cross-section of particles incident on a "stationary" target particle within a given range. However, since the provided reaction cross-section data are based on a laboratory coordinate system, it assumes the target particle is stationary. In reality, the target particle is in thermal motion and its velocity follows a Maxwell distribution. The assumption that the target particle is stationary is an idealized case. Therefore, when using the deuterium-deuterium fusion reaction cross-section, an energy correction is required. The formula for calculating the relative energy is as follows: .

[0030] Therefore, the data for the reaction cross section depends on the relative velocities of the incident and target particles.

[0031] Furthermore, assuming the incident particle is deuterium and has a velocity of... The target particle is deuterium with a velocity of , That is, the relative velocity between the two. Therefore, the relative velocity between the incident deuterium particle and the target deuterium particle can be solved as follows: Figure 3 As shown.

[0032] Furthermore, based on vector subtraction and the cosine theorem, the formula for calculating the relative velocity between the incident deuterium particle and the target deuterium particle is as follows: ; in, Represents the polar angle, which is the ratio of the deuterium velocity of the target particle to... For the included angle of the axis, see Figure 3 As shown.

[0033] Further, see Figure 3 azimuth Characterizing the deuterium velocity of the target particle projected onto Face and The angle between the axes. Under thermal equilibrium conditions, the directional distribution of the deuterium motion of the target particle can be characterized by an isotropic distribution, with the velocity direction passing through ( , This is described using the polar angle. When fixed, for any azimuth angle relative speed Since they are all equal in size, only the polar angle needs to be considered. Discretization can be performed. Velocities of equal magnitude in all directions can form a torus, with the velocity directions at a certain polar angle. Polar weights This is the ratio of the area of ​​the torus to the area of ​​the entire sphere, calculated using the following formula: .

[0034] Furthermore, the velocity magnitude of the deuterated motion of the target particle is discretized. Since the deuterated motion of the target particle follows a Maxwell distribution, the velocity magnitude satisfies: ; Furthermore, the target particle deuterium's motion direction follows an isotropic distribution. When one type of particle participating in the reaction follows a Maxwell distribution while the other is in a non-equilibrium state, the velocity grouping integration method can be used to group the particles following the Maxwell distribution into velocity groups.

[0035] See Figure 4 As shown, the shaded area represents the velocity magnitude weight corresponding to the velocity magnitude group, and the calculation formula is: .

[0036] Therefore, by combining the velocity grouping method, the aforementioned method for temperature correction of the deuterium-deuterium fusion reaction cross section can be realized.

[0037] Through the above settings, this scheme performs temperature correction on the deuterium-deuterium fusion reaction cross-section based on the ENDF database, creating a multi-temperature cross-section database suitable for magnetic confinement fusion, which significantly improves the accuracy of subsequent neutron yield simulation calculations. Furthermore, the multi-temperature fusion differential cross-section database established in this scheme covers a wide temperature range and accurately corrects the reaction cross-section at each temperature node, effectively solving the applicability problem of traditional databases under high-temperature fusion conditions.

[0038] According to one embodiment of the present invention, in step S12, the step of calculating the thermonuclear fusion neutron yield under different combinations of ion density and temperature using a parametric method to construct a thermonuclear fusion neutron yield database, involves constructing the thermonuclear fusion reaction rate based on the parametric method. Formula, and based on thermonuclear fusion reaction rate The formula yields temperatures ranging from 0.5 keV to 10 keV, with a deuterium ion density of... Thermonuclear fusion neutron yield database; In this embodiment, the thermonuclear fusion reaction rate The formula is expressed as: ; ; ; ; ; ; ; in, This represents the volume of the plasma configuration mesh. This represents the initial energy in the energy cluster. This represents the energy after deuterium slowing down. Indicates the density of deuterium ions. The average thermonuclear reaction rate is a function of temperature, indicated by the subscript. , This represents an index of a two-dimensional matrix. Indicates the reaction cross section. , , The three-dimensional coordinates representing the plasma configuration. Indicates the small horizontal radius of the plasma. This represents the angle between the line connecting a point on the magnetic surface to the origin and the horizontal axis. Indicates the circumferential angle, used to describe the position of the plasma in the circumferential direction. This represents the largest radius of the final closed magnetic field. The triangular deformation of plasma, that is, the degree to which the plasma cross-section deviates from a circle, is represented. This represents the small radius of the final closed magnetic field. Expressed as the elongation ratio of the plasma, This indicates the correction of the temperature parameter. Represents energy parameters, This represents the mass of the incident deuterium particle. Represents the speed of light. This represents the Gamow barrier parameter. Indicates the Shavlanov offset. , , , , , and All are constants.

[0039] To further illustrate this scheme, the thermonuclear fusion reaction rate is... The process of constructing the formula will be explained in further detail.

[0040] For thermal deuterium plasma, the calculation of its reaction rate requires integration of the velocity distribution function of the reacting particles based on the Maxwell distribution assumption. Taking the deuterium-deuterium thermonuclear fusion reaction as an example, under thermal equilibrium conditions, the total deuterium-deuterium fusion reaction rate per unit volume can be expressed as: .

[0041] Furthermore, the average thermonuclear reaction rate It can be defined as: ; Furthermore, based on relative energy The average thermonuclear reaction rate can then be calculated. Transform into: ; in, To reduce quality, This represents the mass of the incident deuterium particle. Relative energy This represents the energy cross section.

[0042] In this embodiment, to calculate the thermonuclear fusion reaction rate Then the parameter method is used to determine the average thermonuclear reaction rate. After conversion, you can obtain: ; ; .

[0043] For deuterium-deuterium thermonuclear fusion reactions, when the ion temperature is in the range of [0.2 keV ~ 100 keV], the error between the results calculated using the parametric method and the experimental data is between [0.3% and 0.35%]. The fitting parameters corresponding to different thermonuclear reactions are given in Table 1. The parameters in Table 1... , , , All of these are empirical formulas (i.e., the aforementioned parametric method for the average thermonuclear reaction rate). The parameters involved in the three empirical formulas obtained through the conversion are used to calculate the average thermonuclear reaction rate. .

[0044] Table 1. Fitting parameters for average thermonuclear reaction rate in different fusion reactions.

[0045] Therefore, when the ion temperature is in the range of [0.2keV~100keV], the maximum deviation between the result calculated by the parameter formula and the experimental result does not exceed 2.5%.

[0046] Based on this, the general thermonuclear fusion reaction rate The calculation method is as follows: ; in, For volume.

[0047] Furthermore, in thermal equilibrium, calculating the deuterium-deuterium thermonuclear fusion reaction rate requires discretizing the toroidal plasma of the DEMO reactor in a magnetic coordinate system, as follows: The plasma configuration is meshed, since the ion temperature density distribution of the DEMO stack is determined by parameters. (i.e., the small horizontal radius of the plasma, which is the radius at a specific location) and parameters The mesh is determined by the angle between the line connecting a point on the magnetic surface to the origin and the horizontal axis. Therefore, the mesh generation is based on the parameters. and parameters Discretization is performed, assuming that the ion temperature and density are equal within each grid. The partitioning method is as follows: (1) In the radial direction, based on the Larmor precession and drift of charged particles in a magnetic field, the radial grid spacing can be selected as 1 cm, i.e. Then, the plasma configuration is divided into 250 grids in the radial direction.

[0048] (2) In the angular direction, although the parameter Unlike polar angle, which is the angle between a point on a magnetic surface and the origin. The angle between the line connecting the two axes and the horizontal axis, but the parameter The range of values ​​is still [missing information]. Then, the plasma configuration is divided into 50 grids at the angular direction.

[0049] (3) Thus, the plasma configuration is divided into 250×50 small grids. The grid division result is shown in [reference]. Figure 5 .

[0050] Based on the analytical expression of plasma configuration, the Jacobian determinant method is used to calculate the mesh volume, thus extending the expression for the configuration of the isothermal and isobaric magnetic surface in the tokamak polar coordinate system under magnetohydrodynamic equilibrium conditions to a three-dimensional form. Specifically, the expression for the configuration of the isothermal and isobaric magnetic surface in the tokamak polar coordinate system under magnetohydrodynamic equilibrium conditions is: ; .

[0051] Furthermore, the extended three-dimensional form can be represented as: .

[0052] Furthermore, find the Jacobian determinant: .

[0053] Furthermore, the volume of each small grid cell is obtained through triple integration: .

[0054] Therefore, the thermonuclear fusion reaction rate within each grid can be calculated, thus obtaining the final thermonuclear fusion reaction rate. The formula is expressed as: .

[0055] Furthermore, based on the obtained thermonuclear fusion reaction rate The formula yields the deuterium ion density for temperatures ranging from 0.5 keV to 10 keV. Thermonuclear fusion neutron yield database, and its simulation results are as follows Figure 6 As shown.

[0056] According to one embodiment of the present invention, in step S13, the slowing time and slowing energy spectrum of deuterium ions in plasma under different temperature conditions are calculated using a classical stopping power model, and the target neutron yield is calculated based on a multi-temperature fusion differential cross section database and the slowing energy spectrum to construct a target reaction neutron yield database. In this step, the target reaction rate is constructed based on the multi-temperature fusion differential cross section database and the slowing energy spectrum. The formula yields a neutral beam power of 4 MW at incident particle energies of 75 keV, 70 keV, 60 keV, 50 keV, 40 keV, 30 keV, and 20 keV, at temperatures ranging from 0.5 keV to 10 keV, with a deuterium ion density of [missing value]. Database of neutron yields in beam-target reactions; In this embodiment, the beam-target reaction rate The formula is expressed as: ; ; in, This represents the macroscopic reaction cross section of the deuterium-deuterium fusion reaction. For the slowing process of deuterium ions from the first Energy group slowed down to the first The flux of an energy group, which is physically defined as the average track length of a particle within its volume of motion per unit time. Indicates volume, This represents the sum of the trajectories of all particles within that volume.

[0057] To further illustrate this scheme, the beam-target reaction rate is... The process of constructing the formula will be explained in further detail.

[0058] When high-energy particles propagate within matter, they interact with the components of the medium, resulting in energy loss. It is noteworthy that particles of different energies exhibit differences in their energy loss mechanisms. These mechanisms are closely related to their energy range. Particles in the super-relativistic energy range primarily lose energy through bremsstrahlung; particles in the intermediate relativistic energy range mainly lose energy through ionization, following Bethe's law; while particles in the non-relativistic energy range lose energy through collisions.

[0059] The energy loss rate of charged particles in matter is described by stopping power, which means the energy loss per unit path distance. Energy lost Its expression is as follows: ; in, This represents the energy loss rate of charged particles in matter; The particle's range can then be obtained by the inverse integral of its stopping power, i.e.: ; in, This is the initial incident kinetic energy of the particle. From this, the formula for calculating the slowing-down time of the deuterium particle can be obtained: .

[0060] In the simulation experiment of deuterium ions, relativistic effects are not considered, and its velocity... It can be approximately obtained from the classical kinetic energy formula: .

[0061] Furthermore, in fully ionized plasmas, the stopping power of high-energy particles is typically described using the classical stopping power model: ; ; in, This represents the charge of the incident particle. Indicates the charge number of the target particle. Indicates the mass of the target particle. Represents the Coulomb logarithm. Indicates the first k The density of the plasma components, This represents the average velocity of the target particles. Indicates the temperature of the target particle. express Correction factor This represents a dimensionless velocity parameter used to normalize the velocity of the incident particle relative to the thermal velocity of the plasma components. Indicates the type of target particle, namely deuterium particles; Furthermore, Correction factor The expression is as follows: ; Where erf is the Gaussian error function, which is a non-elementary function, and its expression is as follows: ; in, It represents an integral variable.

[0062] Furthermore, the Coulomb logarithm in the stopping ability expression is a key parameter describing the Coulomb collision process. Its value reflects the relative contribution of small-angle scattering to large-angle scattering in the Coulomb collision; a larger Coulomb logarithm indicates a more significant contribution of large-angle scattering to energy loss. In classical theory, the Coulomb logarithm... The expression is as follows: ; in, This represents the maximum collision parameter, which is equal to the electron Debye length. , This represents the minimum collision parameter, and is... , The collision parameters for the classical least-body Coulomb collision are taken as the scattering parameters at 90°. Let be the de Broglie wavelength of the center of mass in the two-body collision. Temperature is introduced through the following equation: ; in, It is a reduction of quality. , and The mass represents the particle mass, which in this scheme refers to both the deuterium ion mass and the deuterium plasma mass (both are deuterium particle masses). For a single charged particle, the applicable conditions for the classical formula are: ; in, It represents the speed of light.

[0063] Since the rest mass of an electron is 511 keV, the critical temperature associated with it is approximately 10 eV. When the critical temperature is less than 10 eV, quantum mechanical corrections must be introduced. For ions, the critical temperature of a proton is approximately 10 keV, and it increases accordingly with increasing rest mass. The empirical formula for the Coulomb logarithm of the interaction between high-energy charged particles produced by deuterium-deuterium fusion and the background plasma can be described by the following empirical formula: ; in, Represents the coulomb number of an ion. This indicates the mass of the experimental particle; in this case, it is a deuterium particle. This indicates the background plasma mass, which is also deuterium ions in this case. Indicates electron temperature, This represents the energy of the incident particle, specifically the energy of the deuterium ion. It represents electron density.

[0064] Regarding collisions with high-energy charged particles and electrons: ; in, It represents the electron coulomb number.

[0065] Let the initial energy of fast deuterium be... , To determine the energy after rapid deuteration, the number of energy groups is set to... Set the slowing time interval between each energy group to be equal, i.e. , Indicates the slowing time.

[0066] Furthermore, deuterium originates from its initial energy. go through N -1 slowing time The energy is then reduced to thermal deuterium energy. .

[0067] Assuming a simplified isothermal and isodense deuterium plasma experimental model, where the ion temperature and density are uniformly distributed, the background ion temperature is set as a typical value for plasma density in magnetically confined fusion. Based on the aforementioned classical stopping ability model, combined with energy grouping, the moderation time and moderation energy spectrum of deuterium in plasma under different temperature conditions can be obtained by changing the background ion temperature.

[0068] Based on this, for deuterium-deuterium fusion reactions, after neutral beam injection, the deuterium atoms in the beam ionize in the plasma. The non-equilibrium deuterium-deuterium beam-target reaction rate of the ionized deuterium ions during background plasma transport... It can be calculated based on the aforementioned slowing time calculation method and cross-section correction method.

[0069] Therefore, beam-target reaction rate The calculation formula is as follows: ; .

[0070] According to one embodiment of the present invention, in step S2, the ion density of the external experimental equipment is collected. Total neutron production In the process, the external experimental equipment used can be a tokamak device, or other magnetic confinement fusion devices or fusion experimental platforms.

[0071] According to one embodiment of the present invention, in step S4, based on the initial temperature estimate... and ion density Query the neutron yield database and obtain the first neutron yield. Second neutron production And obtain the theoretical total neutron yield. In the first step, the neutron yield The second neutron yield was obtained from a query of the thermonuclear fusion neutron yield database within the neutron yield database. The theoretical total neutron yield was obtained by querying the beam-target reaction neutron yield database within the neutron yield database. Based on the first neutron yield Second neutron production The result can be obtained by summing.

[0072] According to one embodiment of the present invention, in step S5, the initial temperature estimate is adjusted downwards / upwards. Then, update the initial temperature estimate using either the bisection method or the gradient descent method. To temperature estimate In the steps, the bisection method and gradient descent are two typical iterative algorithms, approximating the true solution through different strategies. The bisection method constructs a solution framework based on the intermediate value theorem and utilizes the idea of ​​interval contraction to approach the true solution from the initial temperature range. Initially, repeatedly take the midpoint of the temperature. And based on the theoretical total neutron yield The interval length is reduced based on the relationship between the experimental values ​​and the values ​​until it is less than the tolerance. So far, it requires no derivative and is highly stable, making it suitable for discrete databases and cases where neutron yield is monotonic with temperature, but its convergence is relatively slow. The gradient descent rule defines a loss function... Along the negative gradient direction It iteratively updates the temperature, quickly approximating the minimum point; it converges rapidly but requires derivative information and learning rate to adjust the temperature. It is suitable for continuously differentiable databases and dynamic analysis at multiple time steps, and can be combined with adaptive strategies to improve stability.

[0073] According to one embodiment of the present invention, the magnetic confinement fusion plasma temperature diagnosis method of the present invention further includes: S7. Set a time step to repeat steps S1 to S6 within the time step to obtain the plasma temperature within the current time step, and output the plasma temperature obtained within the current time step as the diagnostic result of the current time step, and use it as the initial temperature of the next time step to complete the temporal evolution analysis of the plasma temperature over the entire time period.

[0074] Through the above settings, this scheme achieves internal and external double-iteration calculations with multiple time steps within a time period, enabling the scheme to accurately and reliably diagnose plasma temperature over long time periods.

[0075] According to one embodiment of the present invention, a magnetic confinement fusion plasma temperature diagnostic device is provided, comprising: a database module, an external data acquisition module, and an iteration module; wherein, the database module is used to establish a neutron yield database, which includes: a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; the external data acquisition module is used to acquire the ion density of external experimental equipment. Total neutron production The iterative module is used to assume that only beam-target reactions exist in the initial stage of the magnetic confinement fusion reaction in the external experimental device, and is based on ion density. Total neutron production The initial temperature estimate was obtained by querying the beam-target reaction neutron yield database. ; and, based on the initial temperature estimate and ion density Query the neutron yield database and obtain the first neutron yield. Second neutron production And obtain the theoretical total neutron yield. Among them, the theoretical total neutron yield ; and, compare total neutron production With theoretical total neutron yield ,like Then lower the initial temperature estimate. Conversely, if Then increase the initial temperature estimate. Among them, adjusting the initial temperature estimate downwards / upwards. When needed, update the initial temperature estimate using either the bisection method or the gradient descent method. To temperature estimate And, based on the updated temperature estimates Regaining the theoretical total neutron yield until The time convergence yields the estimated temperature value at that moment. As the plasma temperature, where... The system sets a preset threshold and outputs the obtained plasma temperature as the diagnostic result at the current moment, and uses it as the initial temperature at the next moment to achieve temporal evolution analysis of plasma temperature.

[0076] Specific limitations regarding the magnetic confinement fusion plasma temperature diagnostic device can be found in the above section on the limitations of vector data extraction methods based on high-fidelity scenarios, and will not be repeated here. Each module in the aforementioned magnetic confinement fusion plasma temperature diagnostic device can be implemented entirely or partially through software, hardware, or a combination thereof. These modules can be embedded in hardware or independently of the processor in a computer device, or stored in software in the memory of a computer device, so that the processor can call and execute the corresponding operations of each module.

[0077] According to one embodiment of the present invention, an apparatus is provided, including at least one processor, at least one memory, and a data bus. In this embodiment, the processor and the memory communicate with each other via the data bus; wherein, the memory stores program instructions executable by the processor, and the processor invokes the program instructions to execute the aforementioned magnetic confinement fusion plasma temperature diagnostic method.

[0078] In this embodiment, the memory may be, but is not limited to, Random Access Memory (RAM), Read Only Memory (ROM), Programmable Read-Only Memory (PROM), Erasable Programmable Read-Only Memory (EPROM), Electrically Erasable Programmable Read-Only Memory (EEPROM), etc.

[0079] In this embodiment, the processor can be an integrated circuit chip with signal processing capabilities. The processor can be a general-purpose processor, including a central processing unit (CPU), a network processor (NP), etc.; it can also be a digital signal processor (DSP), an application-specific integrated circuit (ASIC), a field-programmable gate array (FPGA), or other programmable logic devices, discrete gate or transistor logic devices, or discrete hardware components.

[0080] In this embodiment, the device may also be equipped with a display screen and an input device. The display screen may be an LCD screen or an e-ink screen. The input device may be a touch layer covering the display screen, or a button, trackball, or touchpad set on the housing, or an external keyboard, touchpad, or mouse, etc.

[0081] To further illustrate this plan, further examples will be provided.

[0082] Example Based on the previously established parameters, at a power output of 4MW, the temperature range is 0.5keV to 10keV, and the ion density range is... The neutron yield database was used, and the following results were obtained by combining the above iterative algorithm for ion temperature diagnosis. The bisection simulation results are shown in Table 2: Table 2 Simulation results of the bisection method

[0083] The simulation results of the gradient descent method are shown in Table 3: Table 3 Simulation results of gradient descent method

[0084] Tables 2 and 3 present the ion temperatures obtained from simulated iterative calculations of the input neutron yield using the bisection method and gradient descent method under a fixed ion density, along with detailed results for the beam-target neutron yield and thermonuclear neutron yield at that temperature. The relative errors between the simulated and experimental values ​​are also given. The tables show that regardless of whether the bisection or gradient descent method is used, the simulated ion temperature can be found in the database with a corresponding neutron yield, and the absolute error between the simulated and experimental yields is controlled within 0.1%. This fully demonstrates that, provided the database data is accurate and complete, the simulation iterative method based on the diagnostic system can efficiently and accurately deduce the plasma ion temperature and provide the contributions of the beam-target and thermonuclear reactions to the neutron yield.

[0085] Figure 7 and Figure 8 The convergence process and results comparison of the bisection method and gradient descent method in iterative calculation of ion temperature are presented. The figure shows that the gradient descent method achieves convergence in only 9 steps, a 25% improvement in efficiency compared to the 12 steps of the bisection method, allowing for faster temperature fitting. Furthermore, the simulation reveals that the target neutron yield is significantly higher than the thermonuclear neutron yield, by approximately three orders of magnitude. This verifies that in non-equilibrium plasmas, the target reaction is the primary source of total neutron yield, accounting for over 99%. Therefore, it is feasible to calculate ion temperature using iterative inversion based on neutron yield, provided the database is reliable.

[0086] The above description is merely an example of a specific solution of the present invention. For any devices and structures not described in detail herein, it should be understood that they are implemented using common devices and methods already available in the art.

[0087] The above description is merely one embodiment of the present invention and is not intended to limit the invention. Those skilled in the art will recognize that the present invention can be modified and varied in various ways. Any modifications, equivalent substitutions, or improvements made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

Claims

1. A method for diagnosing the temperature of magnetically confined fusion plasma, characterized in that, Includes the following steps: S1. Establish a neutron yield database, wherein the neutron yield database includes: a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; including: S11. Based on the ENDF database, temperature correction is carried out on the cross section of the deuterium-deuterium fusion reaction under non-equilibrium conditions in order to establish a multi-temperature fusion differential cross section database applicable to non-equilibrium plasma; S12. The thermonuclear fusion neutron yield under different combinations of ion density and temperature is calculated using the parametric method to construct the thermonuclear fusion neutron yield database; S13. Using the classical stopping power model, calculate the slowing time and slowing energy spectrum of deuterium ions in plasma under different temperature conditions, and calculate the target neutron yield based on the multi-temperature fusion differential cross section database and the slowing energy spectrum to construct the target reaction neutron yield database. S2. Collect the ion density from external experimental equipment. Total neutron production ; S3. Assuming that the initial stage of the magnetic confinement fusion reaction in the external experimental device only involves beam-target reaction, and based on ion density... Total neutron production The initial temperature estimate was obtained by querying the neutron yield database of the beam-target reaction. ; S4. Based on the initial temperature estimate and ion density Query the neutron yield database and obtain the first neutron yield. Second neutron production And obtain the theoretical total neutron yield. Among them, the theoretical total neutron yield for ; S5. Comparison of total neutron production With theoretical total neutron yield ,like Then lower the initial temperature estimate. Conversely, if Then increase the initial temperature estimate. Among them, adjusting the initial temperature estimate value downwards / increasing upwards. Then, update the initial temperature estimate using either the bisection method or the gradient descent method. To temperature estimate And, based on the updated temperature estimates Repeat steps S4 to S5 until... The time convergence yields the estimated temperature value at that moment. As the plasma temperature, where... The preset threshold; S6. Output the obtained plasma temperature as the diagnostic result at the current moment, and use the diagnostic result as the initial temperature at the next moment. Repeat steps S4 to S6 to achieve the temporal evolution analysis of plasma temperature.

2. The method for diagnosing the temperature of magnetically confined fusion plasma according to claim 1, characterized in that, In step S11, the step of performing temperature correction on the deuterium-deuterium fusion reaction cross section under non-equilibrium state based on the ENDF database uses the ENDF / B-VII database and combines it with the velocity grouping method to perform temperature correction on the deuterium-deuterium fusion reaction cross section that occurs during the slowing process of deuterium plasma at a specific temperature with deuterium ions incident on it.

3. The method for diagnosing the temperature of magnetically confined fusion plasma according to claim 2, characterized in that, Step S11, which involves performing temperature correction on the deuterium-deuterium fusion reaction cross section under non-equilibrium conditions based on the ENDF database to establish a multi-temperature fusion differential cross section database suitable for non-equilibrium plasmas, includes: S111. Assuming the target particle deuterium is in thermal equilibrium, its velocity follows a Maxwell distribution with isotropic velocity direction. The initial energy of the input incident particle deuterium is... The initial temperature of the target particle deuterium ; S112. Discretize the target particle deuterium velocity magnitude and polar angle into groups, and calculate the velocity magnitude weights for each group. and polar angle weight ; S113. Select the target deuterium particle and the incident deuterium particle from a certain group after grouping, and calculate the relative velocity between the target deuterium particle and the incident deuterium particle. and relative energy ; S114. Based on the relative energy The microscopic reaction cross section between an incident deuterium particle of a given energy and a target deuterium particle of a certain energy group is obtained by interpolation in the ENDF / B-VII database. ; S115. Repeat steps S111 to S114 to obtain the velocity magnitude and direction of the target particle deuterium for all energy groups, and perform a weighted summation on all grouping results to obtain the temperature-corrected microscopic reaction cross section. To establish a multi-temperature fusion differential cross section database applicable to non-equilibrium plasmas.

4. The method for diagnosing the temperature of magnetically confined fusion plasma according to claim 3, characterized in that, In step S112, the target particle deuterium velocity magnitude and polar angle are discretized by grouping, and the velocity magnitude weight of each group is calculated respectively. and polar angle weight In the steps, the speed magnitude weight Represented as: in, Indicates speed The ratio of particles below, i.e., velocity The probability of the number of particles falling out of the total number of particles. This represents the velocity of the deuterium particle. Indicates the mass of a deuterium particle. Represents the Boltzmann constant. Indicates the initial temperature of the target particle deuterium; The polar angle weight Represented as: in, Represents solid angle, This represents the polar angle, i.e., the velocity of the target particle deuterium. y The included angle of the axis; In step S113, target deuterium particles and incident deuterium particles from a certain group after grouping are selected, and the relative velocities of the target deuterium particles and incident deuterium particles are calculated. and relative energy In the steps, the relative energy Represented as: in, Indicates the mass of a deuterium particle. This represents the relative velocity between the target particle deuterium and the incident particle deuterium; In step S115, steps S111 to S114 are repeated to obtain the velocity magnitude and direction of the target particle deuterium for all energy groups. The results of all groupings are then weighted and summed to obtain the temperature-corrected microscopic reaction cross section. In the steps, the temperature-corrected microscopic reaction cross section Represented as: in, Indicates speed The speed magnitude weights are as follows: Indicates speed Polar angle weights, subscripts , This represents a number of a two-dimensional matrix.

5. The method for diagnosing the temperature of magnetically confined fusion plasma according to claim 4, characterized in that, In step S12, the thermonuclear fusion neutron yield is calculated using a parametric method under different combinations of ion density and temperature to construct the thermonuclear fusion neutron yield database. In this step, the thermonuclear fusion reaction rate is constructed based on the parametric method. Formula, and based on the thermonuclear fusion reaction rate The formula yields temperatures ranging from 0.5 keV to 10 keV, with a deuterium ion density of... Thermonuclear fusion neutron yield database; The thermonuclear fusion reaction rate The formula is expressed as: in, This represents the volume of the plasma configuration mesh. This represents the initial energy in the energy cluster. This represents the energy after deuterium slowing down. Indicates the density of deuterium ions. The average thermonuclear reaction rate is a function of temperature, indicated by the subscript. , This represents an index of a two-dimensional matrix. Indicates the reaction cross section. , , The three-dimensional coordinates representing the plasma configuration. Indicates the small horizontal radius of the plasma. This represents the angle between the line connecting a point on the magnetic surface to the origin and the horizontal axis. Indicates the circumferential angle, used to describe the position of the plasma in the circumferential direction. This represents the largest radius of the final closed magnetic field. The triangular deformation of plasma, that is, the degree to which the plasma cross-section deviates from a circle, is represented. This represents the small radius of the final closed magnetic field. Expressed as the elongation ratio of the plasma, This indicates the correction of the temperature parameter. Represents energy parameters, This represents the mass of the incident deuterium particle. Represents the speed of light. This represents the Gamow barrier parameter. Indicates the Shavlanov offset. , , , , , and All are constants.

6. The method for diagnosing the temperature of magnetically confined fusion plasma according to claim 5, characterized in that, In step S13, the slowing time and slowing energy spectrum of deuterium ions in plasma under different temperature conditions are calculated using a classical stopping power model. Based on the multi-temperature fusion differential cross section database and the slowing energy spectrum, the beam target neutron yield is calculated to construct the beam target reaction neutron yield database. In this step, the slowing time and slowing energy spectrum of deuterium ions in plasma under different temperature conditions are calculated using a classical stopping power model. Based on the multi-temperature fusion differential cross section database and the slowing energy spectrum, the beam target reaction rate is constructed. The formula yields a neutral beam power of 4 MW at incident particle energies of 75 keV, 70 keV, 60 keV, 50 keV, 40 keV, 30 keV, and 20 keV, at temperatures ranging from 0.5 keV to 10 keV, with a deuterium ion density of [missing value]. Database of neutron yields in beam-target reactions; The beam target reaction rate The formula is expressed as: in, This represents the macroscopic reaction cross section of the deuterium-deuterium fusion reaction. For the slowing process of deuterium ions from the first Energy group slowed down to the first The flux of an energy group, which is physically defined as the average track length of a particle within its volume of motion per unit time. Indicates volume, This represents the sum of the trajectories of all particles within that volume.

7. The method for diagnosing the temperature of magnetically confined fusion plasma according to claim 6, characterized in that, Also includes: S7. Set a time step to repeat steps S1 to S6 within the time step to obtain the plasma temperature within the current time step, and output the plasma temperature obtained within the current time step as the diagnostic result of the current time step, and use it as the initial temperature of the next time step to complete the temporal evolution analysis of the plasma temperature over the entire time period.

8. A magnetic confinement fusion plasma temperature diagnostic device for use in the magnetic confinement fusion plasma temperature diagnostic method according to any one of claims 1 to 7, characterized in that, include: A database module is used to establish a neutron yield database, wherein the neutron yield database includes: a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; The external data acquisition module is used to collect the ion density of external experimental equipment. Total neutron production ; The iterative module is used to assume that only beam-target reactions exist in the initial stage of the magnetic confinement fusion reaction in the external experimental device, and is based on ion density. Total neutron production The initial temperature estimate was obtained by querying the neutron yield database of the beam-target reaction. ;as well as, Based on initial temperature estimates and ion density Query the neutron yield database and obtain the first neutron yield. Second neutron production And obtain the theoretical total neutron yield. Among them, the theoretical total neutron yield ;as well as, Comparison of total neutron production With theoretical total neutron yield ,like Then lower the initial temperature estimate. Conversely, if Then increase the initial temperature estimate. Among them, adjusting the initial temperature estimate value downwards / increasing upwards. Then, update the initial temperature estimate using either the bisection method or the gradient descent method. To temperature estimate And, based on the updated temperature estimates Regaining the theoretical total neutron yield until The time convergence yields the estimated temperature value at that moment. As the plasma temperature, where... The preset threshold; Furthermore, the obtained plasma temperature is output as the diagnostic result at the current moment and used as the initial temperature at the next moment to achieve temporal evolution analysis of plasma temperature.

9. A temperature diagnostic device for magnetic confinement fusion plasma, characterized in that, Includes at least one processor, at least one memory, and a data bus; The processor and the memory communicate with each other via the data bus; The memory stores program instructions that can be executed by the processor, which invokes the program instructions to execute the magnetic confinement fusion plasma temperature diagnostic method according to any one of claims 1 to 7.

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