A method and system for diagnosing plasma energy storage in a quasi-cyclic symmetric star imitator

Abstract

The application provides a kind of quasi-ring symmetry stellator plasma energy storage diagnostic method and system, it is related to stellator technical field, including adjusting the temperature drift resistance of inverse magnetic differential integrator, according to general discharge waveform, the energization test of quasi-ring symmetry configuration vacuum field magnet coil is carried out, and then the calibration of inverse magnetic differential integrator is completed;Respectively measure and calculate the compensation coefficient of each magnet coil;In the vacuum condition, the same coil configuration parameter is carried out in the plasma discharge experiment of quasi-ring symmetry stellator test device, and the wall eddy current stray field data under corresponding condition is obtained;Combined with the compensation coefficient of magnet coil and wall eddy current stray field data, the real inverse magnetic flux in plasma discharge experiment is calculated;And then the real plasma energy storage information in plasma discharge is calculated.The beneficial effects of the application are to improve the measurement accuracy of plasma energy storage signal in stellator device, and to provide experimental data support for stellator plasma physics research.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of stellarator, in particular to a method and system for diagnosing plasma energy storage in quasi-axisymmetric stellarator. BACKGROUND

[0002] The magnetic measurement system is the core component of the magnetic confinement fusion experimental device operation and research, which is used to obtain important parameters in the device operation process, such as magnetic field distribution, current distribution and other information. In the magnetic measurement system, the core task of the inverse magnetic coil measurement module is to obtain the plasma energy storage information, and further calculate the energy confinement time through these information, which plays an important role in the in-depth study and operation optimization of stellarator physical experiment.

[0003] At present, the traditional concentric circular coil design applied to tokamak device is suitable for its two-dimensional axisymmetric magnetic configuration, but when it is directly applied to the complex quasi-axisymmetric stellarator, especially the Chinese first quasi-axisymmetric stellarator test device (CFQS-T), there are two core defects. One is the precision problem, the three-dimensional twisted vacuum chamber and the complex external coil system of the stellarator will produce unavoidable stray magnetic field interference; the second is the sensitivity problem, the inverse magnetic signal generated by the quasi-axisymmetric stellarator test device in the low parameter operation stage is extremely weak, and the single-turn winding method used by the traditional inverse magnetic coil is difficult to capture effective signal due to low signal-to-noise ratio. Therefore, the existing technology cannot meet the needs of high-precision diagnosis of the new generation of quasi-axisymmetric stellarator, and a new design is needed to break through the above bottleneck. SUMMARY

[0004] The purpose of the present application is to provide a method and system for diagnosing plasma energy storage in quasi-axisymmetric stellarator to improve the above problems. In order to achieve the above purpose, the technical scheme adopted by the present application is as follows:

[0005] In the first aspect, the present application provides a method for diagnosing plasma energy storage in quasi-axisymmetric stellarator, comprising:

[0006] Adjusting the temperature drift resistance of the inverse magnetic differential integrator to make the temperature drift of each integration channel within a preset range; under vacuum conditions, performing quasi-axisymmetric configuration magnet coil energization test and measurement by the inverse magnetic differential integrator, in the process, controlling the size of the magnet coil current to make the corresponding magnetic field strength reach the preset strength and the flat top segment length of the current meet the preset length requirement, and adjusting the size of the adjustable resistance value of the inverse magnetic differential integrator to make the output of the inverse magnetic differential integrator after compensation by the adjustable resistance approach zero, thereby completing the calibration of the inverse magnetic differential integrator;

[0007] Based on the calibrated inverse magnetic differential integrator, each magnet coil is separately powered under vacuum conditions, and the compensation coefficients of each magnet coil are measured and calculated respectively;

[0008] Under vacuum conditions, the same power experiment as the plasma discharge experiment of the actual quasi-axisymmetric stellarator test device is carried out, the wall vortex term in the experiment is measured by a group of inverse magnetic coils without passing through the inverse magnetic differential integrator, and it is recorded as the stray field data generated by the wall vortex;

[0009] The quasi-axisymmetric stellarator plasma discharge experiment is carried out, the compensation coefficients of the magnet coils and the stray field data generated by the wall vortex are combined, and the real inverse magnetic flux in the plasma discharge experiment is calculated;

[0010] According to the obtained real inverse magnetic flux, the real plasma energy storage information in the plasma discharge is calculated.

[0011] The temperature drift resistance of the inverse magnetic differential integrator is adjusted so that the temperature drift of each integration channel is within a preset range; under vacuum conditions, the quasi-axisymmetric configuration magnet coil power test is performed through the inverse magnetic differential integrator and is measured, in this process, the size of the magnet coil current is controlled, so that the corresponding magnetic field strength reaches the preset strength and the current flat top segment length meets the preset length requirement, and the adjustable resistance value of the inverse magnetic differential integrator is adjusted to make the output of the inverse magnetic differential integrator after compensation approach zero, thereby completing the calibration of the inverse magnetic differential integrator;

[0012] Under the parameter setting of the inverse magnetic differential integrator, the plasma discharge experiment is carried out, and the magnetic flux output by the differential integrator is deducted from the excess toroidal magnetic flux.

[0013] In the process of separately powering each magnet coil under vacuum conditions and measuring and calculating the compensation coefficients of each magnet coil, the magnetic field strength corresponding to the discharge is monitored in real time by the magnetic field strength detection device, and the discharge parameters are adjusted based on the monitoring results to maintain the magnetic field strength in the range of not less than 0.0875T.

[0014] The temperature drift resistance of the inverse magnetic differential integrator is adjusted so that the temperature drift of each integration channel is within a preset range, and the magnet coil power test of the QA configuration is performed under vacuum conditions, and the selection of the coil current configuration parameters is consistent with the actual experimental conditions.

[0015] In a second aspect, the application also provides a plasma energy storage diagnosis system in a quasi-axisymmetric stellarator, comprising:

[0016] The adjusting module is used for adjusting the temperature drift resistance of the inverse magnetic differential integrator, so that the temperature drift of each integration channel is within a preset range; under a vacuum condition, a quasi-circular symmetric configuration magnet coil energization test is performed by using the inverse magnetic differential integrator, and measurement is performed in the process, in which the magnet coil current is controlled to reach a preset intensity and the flat top length of the current meets a preset length requirement, and the adjustable resistance of the inverse magnetic differential integrator is adjusted to make the output of the inverse magnetic differential integrator after compensation approach zero, so that the calibration of the inverse magnetic differential integrator is completed.

[0017] The first measurement module is used for measuring and calculating the compensation coefficient of each magnet coil based on the calibrated inverse magnetic differential integrator under a vacuum condition.

[0018] The second measurement module is used for performing an energization experiment under a vacuum condition, in which the coil configuration parameters are the same as those in the actual quasi-circular symmetric stellarator test device plasma discharge experiment, the wall vorticity term in the experiment is measured by a group of inverse magnetic coils without passing through the inverse magnetic differential integrator, and the wall vorticity generated stray field data is recorded.

[0019] The first calculation module is used for performing a quasi-circular symmetric stellarator test device plasma discharge experiment, and combining the magnet coil compensation coefficient and the wall vorticity generated stray field data to calculate the real inverse magnetic flux in the plasma discharge experiment.

[0020] The second calculation module is used for calculating the real plasma energy storage information in the plasma discharge according to the obtained real inverse magnetic flux.

[0021] In a third aspect, the application further provides a plasma energy storage diagnosis device in a quasi-circular symmetric stellarator, which comprises:

[0022] The memory is used for storing the computer program.

[0023] The processor is used for executing the computer program to realize the steps of the diagnosis method of the plasma energy storage in the quasi-circular symmetric stellarator.

[0024] In a fourth aspect, the application further provides a readable storage medium, and the readable storage medium stores a computer program, and the computer program is executed by a processor to realize the steps of the diagnosis method of the plasma energy storage in the quasi-circular symmetric stellarator.

[0025] The application has the following beneficial effects:

[0026] The design principle of the application is based on Faraday's law of electromagnetic induction, the differential method of concentric anti-magnetic coils is used to calculate the anti-magnetic flux information of the plasma, and then the plasma energy storage and energy confinement time are obtained. Since the anti-magnetic flux is usually very small, and the error magnetic flux generated by external magnetic coils such as modular coils, poloidal field coils and toroidal field coils will significantly affect the measurement accuracy, therefore, precise design and optimization are needed to improve the measurement accuracy of the plasma energy storage information in the stellarator device, and provide more reliable experimental data support for the plasma physics research of the stellarator.

[0027] The application can extract and process extremely small anti-magnetic signals with high precision to meet the strict requirements of plasma energy storage measurement in the quasi-toroidal symmetric stellarator test device. Specifically, the signal-to-noise ratio of the anti-magnetic measurement signal is improved to ensure sensitive capture and accurate restoration of extremely small signals; noise interference is reduced to ensure the accuracy and reliability of the measurement data; the measurement error and instability problems existing in the prior art in the complex magnetic field environment are solved; the diagnostic capability of plasma specific pressure and energy in the quasi-toroidal symmetric stellarator test device is realized, and basic data support is provided for accurate calculation of energy confinement time.

[0028] Other features and advantages of the present application will be set forth in the following description, and in part will become apparent to those skilled in the art from the description, or can be learned by practice of the application as described in the written description and claims. The objects and other advantages of the present application can be realized and achieved by the structure particularly pointed out in the written description, claims, and accompanying drawings. BRIEF DESCRIPTION OF DRAWINGS

[0029] In order to more clearly illustrate the technical solutions of the embodiments of the present application, the following will briefly introduce the drawings needed to be used in the embodiments. It should be understood that the following drawings only show some embodiments of the present application, and therefore should not be regarded as a limitation on the scope. For those skilled in the art, other related drawings can also be obtained without creative labor on the basis of these drawings.

[0030] Figure 1 The diagnostic method flow chart of the plasma energy storage in the quasi-toroidal symmetric stellarator described in the embodiments of the present application;

[0031] Figure 2 The diagnostic system structure schematic diagram of the plasma energy storage in the quasi-toroidal symmetric stellarator described in the embodiments of the present application;

[0032] Figure 3 The diagnostic device structure schematic diagram of the plasma energy storage in the quasi-toroidal symmetric stellarator described in the embodiments of the present application;

[0033] Figure 4A schematic diagram of a concentric diamagnetic coil and a differential integrator for measuring the plasma stored energy in a quasi-circular symmetric stellarator in the method for diagnosing the plasma stored energy in a quasi-circular symmetric stellarator described in the embodiments of the present application;

[0034] Figure 5 A schematic diagram of an actual mechanical model of the concentric diamagnetic coil in the method for diagnosing the plasma stored energy in a quasi-circular symmetric stellarator described in the embodiments of the present application;

[0035] Figure 6 A schematic diagram of the spatial arrangement of the concentric diamagnetic coil on a quasi-circular symmetric stellarator test device in the method for diagnosing the plasma stored energy in a quasi-circular symmetric stellarator described in the embodiments of the present application;

[0036] In the figure: 701, an adjusting module; 702, a first measuring module; 703, a second measuring module; 704, a first calculating module; 705, a second calculating module; 800, a device for diagnosing the plasma stored energy in a quasi-circular symmetric stellarator; 801, a processor; 802, a memory; 803, a multimedia component; 804, an I / O interface; 805, a communication component. DETAILED DESCRIPTION

[0037] In order to make the objectives, technical solutions and advantages of the embodiments of the present application clearer, the technical solutions in the embodiments of the present application will be described clearly and completely below with reference to the drawings in the embodiments of the present application. Obviously, the described embodiments are some but not all of the embodiments of the present application. The components of the embodiments of the present application described and shown in the drawings herein can be arranged and designed in various different configurations. Therefore, the following detailed description of the embodiments of the present application provided in the drawings is not intended to limit the scope of the claimed present application, but merely represents selected embodiments of the present application. Based on the embodiments in the present application, all other embodiments obtained by a person of ordinary skill in the art without creative work fall within the scope of protection of the present application.

[0038] It should be noted that: similar reference numerals and letters represent similar items in the following drawings, therefore, once an item is defined in one drawing, it does not need to be further defined and explained in subsequent drawings. Meanwhile, in the description of the present application, the terms “first”, “second” and the like are only used to distinguish description, and cannot be understood as indicating or implying relative importance.

[0039] Embodiment 1:

[0040] The embodiment provides a method for diagnosing plasma energy storage in a quasi-axisymmetric stellarator. Unlike a tokamak device with a relatively simple magnetic field configuration, the quasi-axisymmetric stellarator has a complex three-dimensional magnetic field structure and a vacuum chamber shape. That is, a traditional concentric circle method based on two coplanar approximate circular coils applied in a tokamak device cannot be directly applied to the quasi-axisymmetric stellarator test device, and it is also difficult to effectively distinguish the weak inverse magnetic flux generated by the plasma from the large background magnetic flux caused by the external magnet coils, especially the toroidal field coils and the modular coils.

[0041] Referring to Figure 1 , the method comprises steps S100, S200, S300, S400 and S500.

[0042] S100, adjust the temperature drift resistance of the inverse magnetic differential integrator, so that the temperature drift of each integration channel is within a preset range; under vacuum conditions, perform a quasi-axisymmetric configuration magnet coil energization test by using the inverse magnetic differential integrator and perform measurement, in the process, control the current size of the magnet coil, so that the corresponding magnetic field strength reaches a preset strength and the flat top section time length of the current meets the preset time length requirement, at the same time, adjust the resistance value of the adjustable resistance of the inverse magnetic differential integrator, so that the output of the inverse magnetic differential integrator after compensation tends to zero, thereby completing the calibration of the inverse magnetic differential integrator.

[0043] It can be understood that in the embodiment, the inner and outer inverse magnetic coils respectively induce the change of magnetic flux, and the high-precision differential integrator is used to process two groups of signals, so as to extract the change characteristics of the extremely small inverse magnetic signal. According to the physical characteristics of the inverse magnetic signal and the experimental measurement requirements, the following key parameters are designed for the inverse magnetic coil measurement module of the quasi-axisymmetric stellarator test device: the distance between the concentric inverse magnetic coils is less than or equal to 0.02 m; the polar cross-sectional area ratio AS / Sout is about 10%; the signal magnitude range is 0.1 mWb to 1 mWb; since the number of turns of the coil hardware involved in the present application is 5 turns, when the integration constant RC is 0.2 ms, the corresponding output signal amplitude is 250 mV to 2500 mV.

[0044] It can be understood that the toroidal magnetic flux is deducted through the calibration experiment. Adjust the temperature drift resistance of the differential integrator, so that the temperature drift of each integration channel is less than 5 mV / 10s; under vacuum conditions, perform a QA configuration vacuum field magnet coil energization test according to a normal discharge waveform, and in the QA configuration vacuum field magnet coil energization test process, control the magnetic field strength corresponding to the discharge to be not less than 0.0875 T, and the flat top section time length of the discharge to be greater than 1s; adjust the adjustable resistance , so that the output after compensation is as close to 0 as possible (less than 5 mV / 1s, the remaining part not deducted clean will be deducted in the next step).

[0045] Through optimized antimagnetic coil design, the module can efficiently capture and process antimagnetic signals in complex magnetic field environments, ensuring high-resolution data output.

[0046] In this step, it is via, as Figure 4 The formula for calculating the magnetic flux signal output by the inverse magnetic differential integrator circuit shown is as follows:

[0047]

[0048] In the formula, The total magnetic flux is measured after the signal from the inverse magnetic coil passes through a differential integrator. The fixed resistor is for the inverse magnetic differential integrator. C is the adjustable resistor of the inverse magnetic differential integrator, and C is the fixed capacitor of the differential integrator. The original signal measured from the inner coil of the concentric reverse magnetic coil. The original signal is measured from the outer coil of the concentric diamagnetic coil, and dt is a time infinitesimal element. The circumferential magnetic flux generated by the modular magnet coil, measured on the outer ring of the concentric reverse magnetic coil. The circumferential magnetic flux generated by the MC coil is measured in the inner coil of the concentric reverse magnetic coil. The target inverse magnetic flux is determined by adjusting the value of the adjustable resistor in the inverse magnetic differential integrator so that the output of the inverse magnetic differential integrator after adjustable resistor compensation approaches zero. The calculation formula is as follows:

[0049]

[0050] In the formula, The total magnetic flux is measured after the signal from the inverse magnetic coil passes through a differential integrator. The fixed resistor is for the inverse magnetic differential integrator. The variable resistor is the inverse magnetic differential integrator, and dt is the time infinitesimal element. The circumferential magnetic flux generated by the modular magnet coil, measured on the outer ring of the concentric reverse magnetic coil. The circumferential magnetic flux generated by the MC coil is measured in the inner coil of the concentric reverse magnetic coil. For the target reverse magnetic flux;

[0051] Under the parameter settings of the inverse magnetic differential integrator, a plasma discharge experiment was conducted. The magnetic flux output by the differential integrator was reduced by the excess circumferential magnetic flux. The calculation formula for the magnetic flux signal output by the inverse magnetic differential integrator is as follows:

[0052]

[0053] In the formula, is the total magnetic flux measured by the differential integrator after the diamagnetic coil signal passes through the differential integrator, is the fixed resistance of the diamagnetic differential integrator, is the adjustable resistance of the diamagnetic differential integrator, C is the fixed capacitance of the differential integrator, is the poloidal magnetic flux generated by the MC coil measured by the outer coil of the concentric diamagnetic coil, is the poloidal magnetic flux generated by the MC coil measured by the inner coil of the concentric diamagnetic coil, is the target diamagnetic magnetic flux, is the area of the inner coil in the concentric diamagnetic coil, is the area of the outer coil in the concentric diamagnetic coil, is the magnetic coil poloidal stray field allowance not deducted by the concentric diamagnetic coil, is the stray magnetic flux of the wall eddy current and plasma current measured by the outer coil of a set of concentric diamagnetic coils.

[0054] S200, based on the calibrated diamagnetic differential integrator, separately energize each magnet coil under vacuum conditions, and measure and calculate the compensation coefficient of each magnet coil.

[0055] It can be understood that the calculation formula of this step is as follows:

[0056]

[0057] In the formula, is the magnetic coil poloidal stray field allowance not deducted by the concentric diamagnetic coil, is the compensation coefficient of each modular coil of the quasi-toroidal symmetric stellarator test device, is the current of each modular coil of the quasi-toroidal symmetric stellarator test device, is the compensation coefficient of each poloidal field coil of the quasi-toroidal symmetric stellarator test device is the current of each poloidal field coil of the quasi-toroidal symmetric stellarator test device, is the compensation coefficient of the inner poloidal field coil of the quasi-toroidal symmetric stellarator test device, is the current of the inner poloidal field coil of the quasi-toroidal symmetric stellarator test device, is the compensation coefficient of the outer poloidal field coil of the quasi-toroidal symmetric stellarator test device, is the current of the outer poloidal field coil of the quasi-toroidal symmetric stellarator test device.

[0058] It should be noted that in the step of separately energizing each magnet coil under vacuum conditions and measuring and calculating the compensation coefficient of each magnet coil, the magnetic field strength detection device is used to monitor the magnetic field strength corresponding to the discharge in real time, and the discharge parameters are adjusted based on the monitoring results to maintain the magnetic field strength in the range of not less than 0.875T.

[0059] S300, the same coil configuration parameters as the actual quasi-axisymmetric stellarator test device plasma discharge experiment under vacuum conditions are carried out, the wall vortex item in the experiment is measured by a group of inverse magnetic coils without inverse magnetic differential integrator, and it is recorded as the stray field data generated by the wall vortex.

[0060] It can be understood that the calculation formula of this step is as follows:

[0061]

[0062] In the formula, The stray field magnetic flux generated by the wall vortex of the quasi-axisymmetric stellarator test device, The stray field magnetic flux generated by the plasma current of the quasi-axisymmetric stellarator test device, The stray magnetic flux of the wall vortex and the plasma current measured by the outer coil of a group of concentric inverse magnetic coils.

[0063] It should be noted that in the actual quasi-axisymmetric stellarator test device plasma discharge experiment, the concentric inverse magnetic coil method is used to measure the inverse magnetic flux, wherein the components generated by the modular coil, the poloidal field coil, the toroidal field coil, the vacuum chamber wall vortex and the plasma current in the direction of the inverse magnetic coil will also affect the measurement result, and the calculation formula is as follows:

[0064] 0036.

[0065] In the formula, The total magnetic flux measured by the inverse magnetic coil signal after passing through the differential integrator, The toroidal stray field excess of the magnetic coil not deducted by the concentric inverse magnetic coil, The stray field magnetic flux generated by the wall vortex of the quasi-axisymmetric stellarator test device, The stray field magnetic flux generated by the plasma current of the quasi-axisymmetric stellarator test device.

[0066] It should be noted that in this step, a set of anti-magnetic coils not passing through the anti-magnetic differential integrator is introduced for independent measurement, and the core benefit is to accurately separate and quantify the stray field generated by dynamic effect. Specifically, the independent calibration of each magnet coil in S200 step cannot completely simulate the vacuum chamber wall eddy current induced by the rapid change of magnetic field during plasma discharge, nor can it include the stray magnetic field generated by the plasma current itself. This step ingeniously solves this problem: it measures the two kinds of dynamically changing stray field signals that are difficult to separate in independent calibration as a basic data in advance. This pre-measurement provides key data for accurate correction in the subsequent S400 step, thereby improving the signal-to-noise ratio and accuracy of extracting the real anti-magnetic magnetic signal from the mixed signal, and is a necessary link to achieve high-precision diagnosis.

[0067] S400, carry out quasi-circular symmetric simulator test device plasma discharge experiment, combine the stray field data of the wall eddy current and the compensation coefficient of the magnet coil, and calculate the real anti-magnetic magnetic flux in the plasma discharge experiment.

[0068] It can be understood that the calculation formula of this step is as follows:

[0069]

[0070] In the formula, is the target anti-magnetic magnetic flux, is the integrator electrical parameter measured in the calibration experiment, is the total magnetic flux signal measured after the anti-magnetic coil signal in the plasma discharge experiment passes through the differential integrator, is the compensation coefficient of each modular coil of the quasi-circular symmetric simulator test device, is the current of each modular coil of the quasi-circular symmetric simulator test device, is the compensation coefficient of each toroidal field coil of the quasi-circular symmetric simulator test device is the current of each toroidal field coil of the quasi-circular symmetric simulator test device, is the compensation coefficient of the poloidal field coil inside the quasi-circular symmetric simulator test device, is the current of the poloidal field coil inside the quasi-circular symmetric simulator test device, is the compensation coefficient of the poloidal field coil outside the quasi-circular symmetric simulator test device, is the current of the poloidal field coil outside the quasi-circular symmetric simulator test device, is the wall eddy current and plasma current stray magnetic flux measured by the outer coil of a set of concentric anti-magnetic coils.

[0071] It should be noted that in this step, the real plasma diamagnetic magnetic flux is obtained by deducting the influence of the stray magnetic field generated by the magnet coil in the direction of the concentric diamagnetic coil and the wall vortices and plasma current, and the stray field brought by the wall vortices is mainly in the magnet coil current rising and falling section, and in the plasma discharge stable stage (also the magnet coil current stable stage) The stray field brought by the wall vortices to the diamagnetic measurement is very small and can be ignored.

[0072] S500, according to the obtained real diamagnetic magnetic flux, the real plasma energy storage information in the plasma discharge is calculated.

[0073] It can be understood that the calculation formula of this step is as follows:

[0074]

[0075] In the formula, is the plasma energy storage, is the device major radius, is the magnetic field strength at the magnetic axis, is the target diamagnetic magnetic flux, is the vacuum permeability.

[0076] In this embodiment, the multi-turn coil winding mode is selected according to the special requirements of the diamagnetic coil, so as to improve the signal-to-noise ratio and output amplitude of the signal. For example, when the diamagnetic magnetic flux is 0.1 mWb, a 0.2 ms integrator time constant is used, and the measurement signal of the 5-turn diamagnetic coil can be enhanced to 250 mV, which meets the requirements of high sensitivity signal acquisition.

[0077] In addition, the module uses a high-precision sliding resistor to adjust the differential signal, and the differential integrator output is very close to zero in the absence of plasma. In the experimental state, the signal output by the integrator directly reflects the diamagnetic magnetic signal of the plasma, thereby realizing accurate measurement of the energy storage.

[0078] It should be noted that for different operating states that may occur in the quasi-toroidal symmetric stellarator test device, the adjustable integrator time constant and the differential parameter are used to optimize the dynamic response range and measurement sensitivity of the module. For example, in the case of diamagnetic flux of 0.1 mWb to 1 mWb, by adjusting the time constant to 0.2 s, 0.5 s or 1 s, different experimental scenarios can be adapted. The module design is compatible with multiple experimental scenarios and can adapt to different operating requirements and support future functional expansion.

[0079] That is, in this embodiment, the diamagnetic coil module makes key adaptive creations in physical design to solve this core technical challenge, and the content is as follows:

[0080] 1. Special geometry of the diamagnetic coil design: The diamagnetic coil of the present application abandons the traditional planar circular design and adopts a special shaped configuration. The diamagnetic coil and its peripheral mechanical support and protection structure are precisely calculated and optimized, so that they can closely fit the complex three-dimensional profile of the inner wall of the vacuum chamber of the quasi-axisymmetric stellarator test device, as shown in Figure 5 , and the relative position of its installation on the quasi-axisymmetric stellarator test device is as shown in Figure 6 . This design ensures that the diamagnetic coil can surround the plasma to the greatest extent, and is also conducive to increasing the distance from the plasma, thereby more accurately measuring the diamagnetic flux of the plasma and protecting the diamagnetic coil and reducing the thermal load on the mechanical structure of the diamagnetic coil.

[0081] 2. Parallel coplanar arrangement with a specific toroidal field coil: When designing the path of the diamagnetic coil arranged in the polar direction, a specific toroidal field coil (TFC) of the quasi-axisymmetric stellarator test device is taken as a reference to ensure that the diamagnetic coil maintains parallelism with the toroidal field coil (TFC) as much as possible at each polar position and in a plane. This key design makes the magnetic flux generated by the toroidal field coil as perpendicular to the plane where the diamagnetic coil is located as possible, which is conducive to more strictly compensating the stray field generated by the toroidal field coil and provides the necessary premise for measuring the diamagnetic signal as low as 0.1 mWb.

[0082] 3. High-precision installation and positioning: Given the complex structure of the stellarator, accurate installation and positioning of the inner and outer concentric diamagnetic coils are crucial. The present application requires the use of a high-precision laser tracker for auxiliary installation and positioning to ensure that the inner and outer diamagnetic coils can maintain the same plane and a spacing Δl ≤ 0.02 m throughout the complex path, which is the physical basis for accurate differential measurement and effectively avoids measurement errors introduced by the inner and outer diamagnetic coils not being in the same plane.

[0083] In summary, this design, which is tailored to the three-dimensional physical characteristics of the quasi-axisymmetric stellarator test device, closely fits the vacuum chamber wall and is arranged parallel to a specific toroidal field coil, is the key point of the present application to achieve high signal-to-noise ratio and high-precision measurement of extremely small diamagnetic signals in a high background magnetic field interference, effectively solving the technical difficulties of traditional measurement methods that are difficult to adapt to complex three-dimensional magnetic confinement configurations.

[0084] Embodiment 2:

[0085] As shown in Figure 2 , the present embodiment provides a system for diagnosing the energy storage of plasma in a quasi-axisymmetric stellarator, as shown in Figure 2 The system comprises:

[0086] The adjustment module 701 is used for adjusting the temperature drift resistance of the inverse magnetic differential integrator, so that the temperature drift of each integration channel is within a preset range; under vacuum conditions, the quasi-circular symmetric configuration magnet coil energization test is performed by the inverse magnetic differential integrator, and measurement is performed, in the process, the magnet coil current is controlled to reach a preset intensity, and the flat top length of the current meets the preset length requirement, and the adjustable resistance value of the inverse magnetic differential integrator is adjusted, so that the output of the inverse magnetic differential integrator after compensation approaches zero, and the calibration of the inverse magnetic differential integrator is completed.

[0087] The first measurement module 702 is used for measuring and calculating the compensation coefficient of each magnet coil based on the calibrated inverse magnetic differential integrator under vacuum conditions.

[0088] The second measurement module 703 is used for carrying out the energization experiment under the same coil configuration parameters as the actual quasi-circular symmetric star simulator test device plasma discharge experiment under vacuum conditions, the wall vortex term in the experiment is measured by a group of inverse magnetic coils without passing through the inverse magnetic differential integrator, and is recorded as the stray field data generated by the wall vortex;

[0089] The first calculation module 704 is used for carrying out the quasi-circular symmetric star simulator test device plasma discharge experiment, combining the magnet coil compensation coefficient and the stray field data generated by the wall vortex, and calculating the real inverse magnetic flux in the plasma discharge experiment.

[0090] The second calculation module 705 is used for calculating the real plasma energy storage information in the plasma discharge according to the obtained real inverse magnetic flux.

[0091] The module of the application adopts a high-precision differential integrator, and combines the accurate installation of two concentric inverse magnetic coils to ensure accurate processing of signals. For example, the distance Δl of the inverse magnetic coils is controlled within the range of ≤0.02 m, and the cross-sectional area ratio ΔS / Sout of the inverse magnetic coils is optimized to about 10%, so as to optimize the measurement signal quality and resolution.

[0092] It should be noted that, in order to ensure the stable operation of the module under extreme experimental conditions, the application adopts a high-temperature-resistant and radiation-resistant material as the module shell, and optimizes the protection measures of the electronic components. The module design fully considers the electromagnetic interference factors in the experimental environment, and significantly improves the overall reliability and adaptability through multi-layer shielding and anti-interference circuit design. Under the high temperature and low pressure environment in the vacuum chamber of the quasi-circular symmetric star simulator test device, the inverse magnetic coil module can stably output signals while ensuring extremely low signal drift.

[0093] In summary, the module for measuring plasma stored energy in the magnetic confinement configuration device is different from other modules, which can significantly improve the measurement accuracy. Through the design of the inner and outer double-layer concentric inverse magnetic coils and high-precision signal processing technology, the resolution and measurement accuracy of the inverse magnetic signal are effectively improved, and the detection of the small inverse magnetic signal is ensured. For example, the module successfully realizes the accurate measurement of the plasma with a stored energy signal of 10 J to 100 J. The module significantly improves the applicability and expandability of the inverse magnetic coil measurement module for plasma stored energy. By fully considering the physical characteristics and experimental requirements of the quasi-axisymmetric stellarator test device, the module has flexible adaptability and strong compatibility, which is not only suitable for current experimental requirements, but also can be extended to other quasi-axisymmetric magnetic confinement devices.

[0094] The module also optimizes the signal-to-noise ratio. By combining the multi-turn coil with the optimized electronic processing technology, the signal-to-noise ratio is greatly improved, and the influence of external interference on the measurement data is significantly reduced. In the test, the signal-to-noise ratio is doubled compared to the original system, providing higher reliability for experimental results. The module provides a reliable and efficient technical means for the plasma stored energy measurement of the quasi-axisymmetric stellarator test device, significantly improving the accuracy and efficiency of the energy confinement time research, providing strong support for the in-depth exploration of the stellarator physics field. The flexibility and expandability of the module design provide the possibility for future experimental optimization and functional upgrade, which can meet more diversified experimental requirements and help the scientific research in the field of magnetic confinement fusion to a new height.

[0095] It should be noted that the specific way in which each module performs the operation in the system described above has been described in detail in the embodiment related to the method, and will not be described in detail here.

[0096] Embodiment 3:

[0097] Corresponding to the above method embodiment, the present embodiment also provides a diagnostic device for plasma stored energy in a quasi-axisymmetric stellarator. The diagnostic device for plasma stored energy in a quasi-axisymmetric stellarator described below can be referred to in conjunction with the diagnostic method for plasma stored energy in a quasi-axisymmetric stellarator described above.

[0098] Figure 3 Fig. 8 is a block diagram of a diagnostic device 800 for plasma stored energy in a quasi-axisymmetric stellarator according to an example embodiment. As shown in Fig. 8, the diagnostic device 800 for plasma stored energy in a quasi-axisymmetric stellarator includes a processor 801 and a memory 802. The diagnostic device 800 for plasma stored energy in a quasi-axisymmetric stellarator also includes one or more of a multimedia component 803, an I / O interface 804, and a communication component 805. Figure 3

[0099] ​The processor 801 is configured to control overall operation of the quasi-circular symmetric stellarator plasma energy storage diagnostic device 800 to complete all or part of the steps of the quasi-circular symmetric stellarator plasma energy storage diagnostic method described above. The memory 802 is configured to store various types of data to support the operation of the quasi-circular symmetric stellarator plasma energy storage diagnostic device 800, which can include, for example, instructions for any application or method operating on the quasi-circular symmetric stellarator plasma energy storage diagnostic device 800, and application-related data, such as contact data, messages sent and received, pictures, audio, video, and the like. The memory 802 can be implemented by any type of volatile or non-volatile storage device or a combination thereof, such as static random access memory (SRAM), electrically erasable programmable read-only memory (EEPROM), erasable programmable read-only memory (EPROM), programmable read-only memory (PROM), read-only memory (ROM), magnetic storage, flash memory, magnetic disk or optical disk. The multimedia component 803 can include a screen and an audio component. The screen can be, for example, a touch screen, and the audio component is configured to output and / or input audio signals. For example, the audio component can include a microphone configured to receive external audio signals. The received audio signals can be further stored in the memory 802 or transmitted through the communication component 805. The audio component also includes at least one speaker configured to output audio signals. The I / O interface 804 provides an interface between the processor 801 and other interface modules, which can be a keyboard, mouse, or buttons, etc. These buttons can be virtual buttons or physical buttons. The communication component 805 is configured to enable wired or wireless communication between the quasi-circular symmetric stellarator plasma energy storage diagnostic device 800 and other devices. Wireless communication, such as Wi-Fi, Bluetooth, near field communication (NFC), 2G, 3G, or 4G, or a combination of one or more of them, so the corresponding communication component 805 can include a Wi-Fi module, a Bluetooth module, or an NFC module.

[0100] In an example embodiment, the plasma energy storage diagnosing device 800 in the quasi-circular symmetric stellarator can be implemented by one or more of Application Specific Integrated Circuit (ASIC), Digital Signal Processor (DSP), Digital Signal Processing Device (DSPD), Programmable Logic Device (PLD), Field Programmable Gate Array (FPGA), controller, microcontroller, microprocessor or other electronic elements to execute the above-mentioned plasma energy storage diagnosing method in the quasi-circular symmetric stellarator.

[0101] In another example embodiment, a computer readable storage medium including program instructions is also provided, which, when executed by a processor, implement the steps of the above-mentioned plasma energy storage diagnosing method in the quasi-circular symmetric stellarator. For example, the computer readable storage medium can be the above-mentioned memory 802 including program instructions, which can be executed by the processor 801 of the plasma energy storage diagnosing device 800 in the quasi-circular symmetric stellarator to complete the above-mentioned plasma energy storage diagnosing method in the quasi-circular symmetric stellarator.

[0102] Embodiment 4:

[0103] Corresponding to the above method embodiments, in this embodiment, a readable storage medium is also provided, which can be referred to in combination with the above-mentioned plasma energy storage diagnosing method in the quasi-circular symmetric stellarator.

[0104] The computer program stored on the readable storage medium can be executed by a processor to implement the steps of the above-mentioned plasma energy storage diagnosing method in the quasi-circular symmetric stellarator.

[0105] The readable storage medium can be specifically a U disk, a mobile hard disk, a Read-Only Memory (ROM), a Random Access Memory (RAM), a magnetic disk or an optical disk, and various readable storage media that can store program codes.

[0106] The above description is merely a preferred embodiment of the present invention and is not intended to limit the invention. Various modifications and variations can be made to the present invention by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

[0107] The above description is merely a specific embodiment of the present invention, but the scope of protection of the present invention is not limited thereto. Any variations or substitutions that can be easily conceived by those skilled in the art within the technical scope disclosed in the present invention should be included within the scope of protection of the present invention. Therefore, the scope of protection of the present invention should be determined by the scope of the claims.

Claims

1. A diagnostic method for plasma energy storage in a quasi-toroidal stellarator, characterized in that, include: Adjust the temperature drift resistor of the inverse magnetic differential integrator to ensure that the temperature drift of each integration channel is within the preset range; under vacuum conditions, perform a quasi-loop symmetrical configuration magnet coil energization test and measurement through the inverse magnetic differential integrator. During this process, control the magnitude of the magnet coil current so that the corresponding magnetic field strength reaches the preset strength and the duration of the current flat-top segment meets the preset duration requirement. At the same time, adjust the value of the adjustable resistor of the inverse magnetic differential integrator so that the output of the inverse magnetic differential integrator after adjustable resistor compensation approaches zero, thereby completing the calibration of the inverse magnetic differential integrator. Based on the calibrated inverse magnetic differential integrator, each magnet coil is individually energized under vacuum conditions, and the compensation coefficient of each magnet coil is measured and calculated. Under vacuum conditions, an energizing experiment was conducted with the same coil configuration parameters as in the plasma discharge experiment of the actual quasi-ring symmetric stellarator test device. The wall eddy current term in the experiment was measured by a set of inverse magnetic coils without passing through the inverse magnetic differential integrator, and recorded as the stray field data generated by the wall eddy current. Plasma discharge experiments were conducted on a quasi-toroidal stellarator test device. The actual contramagnetic flux in the plasma discharge experiment was calculated by combining the compensation coefficient of the magnet coil and the stray field data generated by the wall eddy current. Based on the obtained true inverse magnetic flux, the true plasma energy storage information in plasma discharge is calculated.

2. The diagnostic method for plasma energy storage in a quasi-toroidal stellarator according to claim 1, characterized in that, The temperature drift resistor of the inverse magnetic differential integrator is adjusted to ensure that the temperature drift of each integration channel is within a preset range. Under vacuum conditions, the quasi-loop symmetrical configuration magnet coil is energized and measured through the inverse magnetic differential integrator. During this process, the magnitude of the magnet coil current is controlled so that the corresponding magnetic field strength reaches a preset strength and the duration of the current peak meets a preset duration requirement. Simultaneously, the value of the adjustable resistor of the inverse magnetic differential integrator is adjusted so that the output of the inverse magnetic differential integrator after adjustable resistor compensation approaches zero, thereby completing the calibration of the inverse magnetic differential integrator. The formula for calculating the magnetic flux signal output by the inverse magnetic differential integrator after adjustable resistor compensation is as follows: In the formula, The total magnetic flux is measured after the signal from the inverse magnetic coil passes through a differential integrator. The fixed resistor is for the inverse magnetic differential integrator. C is the adjustable resistor of the inverse magnetic differential integrator, and C is the fixed capacitor of the differential integrator. The original signal measured from the inner coil of the concentric reverse magnetic coil. The original signal is measured from the outer coil of the concentric diamagnetic coil, and dt is a time infinitesimal element. The circumferential magnetic flux generated by the modular magnet coil, measured on the outer ring of the concentric reverse magnetic coil. The circumferential magnetic flux generated by the MC coil is measured in the inner coil of the concentric reverse magnetic coil. The target inverse magnetic flux is determined by adjusting the value of the adjustable resistor in the inverse magnetic differential integrator so that the output of the inverse magnetic differential integrator after adjustable resistor compensation approaches zero. The calculation formula is as follows: In the formula, The total magnetic flux is measured after the signal from the inverse magnetic coil passes through a differential integrator. The fixed resistor is for the inverse magnetic differential integrator. The variable resistor is the inverse magnetic differential integrator, and dt is the time infinitesimal element. The circumferential magnetic flux generated by the modular magnet coil, measured on the outer ring of the concentric reverse magnetic coil. The circumferential magnetic flux generated by the MC coil is measured in the inner coil of the concentric reverse magnetic coil. For the target reverse magnetic flux; Under the parameter settings of the inverse magnetic differential integrator, a plasma discharge experiment was conducted. The magnetic flux output by the differential integrator was reduced by the excess circumferential magnetic flux. The calculation formula for the magnetic flux signal output by the inverse magnetic differential integrator is as follows: In the formula, The total magnetic flux is measured after the signal from the inverse magnetic coil passes through a differential integrator. The fixed resistor is for the inverse magnetic differential integrator. C is the adjustable resistor of the inverse magnetic differential integrator, and C is the fixed capacitor of the differential integrator. The circumferential magnetic flux generated by the MC coil is measured for the outer coil of the concentric reverse magnetic coil. The circumferential magnetic flux generated by the MC coil is measured in the inner coil of the concentric reverse magnetic coil. For the target reverse magnetic flux, The inner coil area is the area of ​​the concentric reverse magnetic coil. The area of ​​the outer coil in the concentric reverse magnetic coil. This refers to the undeducted circumferential stray field margin of the concentric reverse magnetic coil. The stray magnetic flux of the wall eddy current and plasma current is measured using the outer coil of a set of concentric inverse magnetic coils.

3. The diagnostic method for plasma energy storage in a quasi-toroidal stellarator according to claim 1, characterized in that, The calibrated inverse magnetic differential integrator, under vacuum conditions, individually energizes each magnet coil, and measures and calculates the compensation coefficient of each magnet coil. The calculation formula is as follows: In the formula, This represents the undeducted circumferential stray field margin of the concentric reverse magnetic coil. The compensation coefficients for each modular coil of the quasi-toroidal stellarator test device. To measure the current in each modular coil of the quasi-toroidal stellarator test device. The compensation coefficients of each toroidal field coil in the quasi-toroidal stellarator test setup To measure the current in each toroidal field coil of the quasi-toroidal symmetric stellarator test device. The compensation coefficient for the poloidal field coil within the quasi-ring symmetric stellarator test device. The current in the poloidal field coil within the quasi-toroidal stellarator test device. The compensation coefficient for the outer poloidal field coil of the quasi-ring symmetrical stellarator test device. The current in the outer pole-direction field coil of the quasi-toroidal stellarator test device.

4. The diagnostic method for plasma energy storage in a quasi-toroidal stellarator according to claim 1, characterized in that, The wall eddy current term and plasma current term of the parameter data under the discharge experiment were measured by a set of inverting magnetic coils without passing through the inverting magnetic differential integrator, and their calculation formulas are as follows: In the formula, Stray field magnetic flux generated by eddy currents on the wall of a quasi-toroidal stellarator test device. The stray magnetic flux generated by the plasma current in the quasi-toroidal stellarator test device. The stray magnetic flux of the wall eddy current and plasma current is measured using the outer coil of a set of concentric inverse magnetic coils.

5. The diagnostic method for plasma energy storage in a quasi-toroidal stellarator according to claim 1, characterized in that, The plasma discharge experiment of the quasi-toroidal symmetric stellarator test device was carried out. Based on the magnet coil compensation coefficient and wall eddy current stray field data, the true contramagnetic flux in the plasma discharge experiment was calculated. The calculation formula is as follows: In the formula, For the target reverse magnetic flux, To calibrate the integrator electrical parameters measured in the experiment, This refers to the total magnetic flux signal measured after the signal from the inverse magnetic coil in the plasma discharge experiment passes through a differential integrator. The compensation coefficients for each modular coil of the quasi-toroidal stellarator test device. To measure the current in each modular coil of the quasi-toroidal stellarator test device. The compensation coefficients of each toroidal field coil in the quasi-toroidal stellarator test setup To measure the current in each toroidal field coil of the quasi-toroidal symmetric stellarator test device. The compensation coefficient for the poloidal field coil within the quasi-ring symmetric stellarator test device. The current in the poloidal field coil within the quasi-toroidal stellarator test device. The compensation coefficient for the outer poloidal field coil of the quasi-ring symmetrical stellarator test device. The current in the outer poloidal field coil of the quasi-toroidal stellarator test device. The stray magnetic flux of the wall eddy current and plasma current is measured using the outer coil of a set of concentric inverse magnetic coils.

6. The diagnostic method for plasma energy storage in a quasi-toroidal stellarator according to claim 1, characterized in that, The actual plasma energy storage information in plasma discharge is calculated based on the obtained actual contramagnetic flux, and the calculation formula is as follows: In the formula, For plasma energy storage, For the device to have a large radius, Let be the magnetic field strength at the magnetic axis. For the target reverse magnetic flux, is the vacuum permeability.

7. The diagnostic method for plasma energy storage in a quasi-toroidal stellarator according to claim 1, characterized in that, In the process of individually energizing each magnet coil under vacuum conditions, measuring and calculating the compensation coefficient of each magnet coil, the magnetic field strength corresponding to the discharge is monitored in real time by a magnetic field strength detection device, and the discharge parameters are adjusted based on the monitoring results to maintain the magnetic field strength in the range of not less than 0.0875T.

8. The diagnostic method for plasma energy storage in a quasi-toroidal stellarator according to claim 1, characterized in that, In the energizing experiment conducted under vacuum conditions with the same coil configuration parameters as in the plasma discharge experiment of the actual quasi-toroidal symmetric stellarator test platform device, the concentric reverse magnetic coil method is used to measure the reverse magnetic flux. The components of the magnetic flux generated by the modular coil, poloidal field coil, circumferential field coil, eddy current in the vacuum chamber wall, and plasma current in the measurement direction of the reverse magnetic coil also affect the measurement results. The calculation formula is as follows: In the formula, The total magnetic flux is measured after the signal from the inverse magnetic coil passes through a differential integrator. This represents the undeducted circumferential stray field margin of the concentric reverse magnetic coil. Stray field magnetic flux generated by eddy currents on the wall of a quasi-toroidal stellarator test device. Stray field magnetic flux generated by plasma current in a quasi-toroidal stellarator test device.

9. The diagnostic method for plasma energy storage in a quasi-toroidal stellarator according to claim 1, characterized in that, Adjust the temperature drift resistor of the inverse magnetic differential integrator so that the temperature drift of each integration channel is within the preset range. Perform a QA configuration magnet coil energization test under vacuum conditions, and the selection of its coil current configuration parameters is consistent with the actual experimental conditions.

10. A diagnostic system for plasma energy storage in a quasi-toroidal stellarator, based on the diagnostic method for plasma energy storage in a quasi-toroidal stellarator as described in claim 1, characterized in that, include: Adjustment module: Used to adjust the temperature drift resistance of the inverse magnetic differential integrator so that the temperature drift of each integration channel is within a preset range; under vacuum conditions, the inverse magnetic differential integrator performs a quasi-loop symmetrical configuration magnet coil energization test and measurement. During this process, the magnet coil current is controlled so that the corresponding magnetic field strength reaches the preset strength and the current peak duration meets the preset duration requirement. At the same time, the adjustable resistance value of the inverse magnetic differential integrator is adjusted so that the output of the inverse magnetic differential integrator after adjustable resistance compensation approaches zero, thereby completing the calibration of the inverse magnetic differential integrator. First measurement module: used to individually energize each magnet coil under vacuum conditions based on the calibrated inverse magnetic differential integrator, and measure and calculate the compensation coefficient of each magnet coil respectively; The second measurement module is used to conduct an energizing experiment under vacuum conditions with the same coil configuration parameters as in the plasma discharge experiment of the actual quasi-ring symmetric stellarator test device. The wall eddy current term in the experiment is measured by a set of inverse magnetic coils without passing through the inverse magnetic differential integrator and recorded as the stray field data generated by the wall eddy current. The first calculation module is used to conduct plasma discharge experiments on the quasi-toroidal stellarator test device. It calculates the true contramagnetic flux in the plasma discharge experiment by combining the compensation coefficient of the magnet coil and the stray field data generated by the wall eddy current. The second calculation module is used to calculate the true plasma energy storage information in the plasma discharge based on the obtained true contramagnetic flux.

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