A coupling simulation method and system for a tokamak

Abstract

The application belongs to the technical field of simulation, and discloses a coupling simulation method and system for a tokamak, a computer device and a storage medium. The simulation method comprises the following steps: initializing a plurality of plasma parameters; performing initialization iteration according to the plurality of plasma parameters, and outputting an initialization iteration result; setting an iteration control parameter; the control parameter comprises a time step, a total step number and a current step number; and performing coupling iteration on transport and balance according to the initialization iteration result and the control parameter to obtain a coupling simulation result. The application can guarantee the comprehensiveness of information exchange during tokamak plasma transport and balance simulation, and improve the accuracy of simulation results.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of simulation, in particular to a coupling simulation method and system for a tokamak. BACKGROUND

[0002] With the increasingly serious energy and environmental problems, the demand for developing new green and environmentally friendly energy to replace fossil fuels is becoming more and more urgent, and it is expected to eliminate harmful emissions generated by combustion with new energy. Fusion energy is considered to be the ideal clean energy in the future because of its advantages of no pollution of reaction products and high safety. The tokamak device in magnetic confinement nuclear fusion is currently recognized as the most likely way to achieve commercialization of fusion energy, and the tokamak device is composed of a vacuum chamber, a poloidal field coil, a central solenoid coil, an auxiliary heating system, a diagnostic system and a power supply system and other subsystems. The principle of the tokamak is to generate a special-shaped magnetic field by passing thousands of amperes of large current into the poloidal field coil to confine the high-temperature plasma of hundreds of millions of degrees Celsius. The accurate simulation in the early stage is the guarantee for the good discharge operation of the tokamak, and the balance between the plasma pressure gradient force and the electromagnetic force is the basis for almost all simulations.

[0003] The key input parameter in the tokamak plasma balance calculation is the current profile distribution, which refers to the distribution of the toroidal plasma current density under the magnetic surface coordinate. There are two methods to determine this parameter in the existing simulation: the first method is to assume that the current profile is a certain form of nonlinear function; the second method is to obtain it from experimental measurement. After obtaining the current profile, the value of the poloidal magnetic flux at each point in space is obtained by solving the balance equation. For the first method, the assumed nonlinear function may have a large deviation from the actual situation; for the second method, the experimental measurement value is seriously dependent on the experimental conditions, and the measurement result has errors, and the number of experiments is limited, so the measurement value cannot completely cover all possible situations. Both of the existing two methods may lead to inaccurate simulation results, which may cause the actual engineering discharge failure and even equipment damage.

[0004] In the plasma physics theory, the real current profile should be given by solving the equation group composed of the current diffusion, heat diffusion, external power driving and rotation transport equations satisfied by the core plasma. Meanwhile, the solution of the transport also depends on the equilibrium given poloidal flux distribution, and the two influence each other. In recent years, some foreign researches try to solve the transport and equilibrium coupling, but there are two defects at present: first, only the last closed flux surface LCFS of the poloidal flux is taken as the input of the equilibrium into the transport, and since the magnetic surface shape changes in the radial direction, the boundary magnetic surface is a rough choice; second, the existing researches show that the coupling system composed of the transport and the equilibrium is unstable, and feedback control must be added to realize the stable coupling solution. The existing solution technology has not closely combined the transport and the equilibrium. SUMMARY

[0005] The purpose of the present application is to provide a coupling simulation method and system for tokamak, computer equipment and storage medium, which solves the problem of inaccurate simulation results caused by incomplete information exchange and unstable coupling system composed of transport and equilibrium in the simulation of tokamak plasma transport and equilibrium.

[0006] The present application is realized by the following technical solutions:

[0007] In a first aspect, a coupling simulation method for tokamak is provided, characterized in that it comprises the following steps: initializing a plurality of plasma parameters; performing initialization iteration according to the plurality of plasma parameters, and outputting initialization iteration results; setting iteration control parameters; the control parameters include time step, total number of steps and current number of steps; coupling iteration of transport and equilibrium according to the initialization iteration results and the control parameters, and obtaining coupling simulation results.

[0008] Further, the plurality of plasma parameters include major radius, minor radius, elongation ratio, Shafranov displacement and plasma current.

[0009] Further, before the initialization iteration according to the plurality of plasma parameters, the following steps are included: calling the FEEQS program to process the plurality of plasma parameters, and obtaining the poloidal flux radial distribution, the elongation ratio under the magnetic surface coordinate, the poloidal flux radial distribution and the magnetic surface axis position; setting the same major radius, minor radius, elongation ratio and Shafranov displacement as the plurality of plasma parameters in the METIS program; editing the waveform of auxiliary heating power.

[0010] Further, the initialization iteration is performed according to the plurality of plasma parameters, and the initialization iteration comprises the following steps: performing steps A1 to A4 between the FEEQS program and the METIS program until the poloidal flux radial distribution of the boundary is consistent with the poloidal flux radial distribution on the magnetic axis. In the steps A1, the FEEQS program is called to process the plurality of plasma parameters; in the step A2, the processing result of the FEEQS program is input into the METIS program; in the step A3, the processing result of the FEEQS program is processed in the METIS program, and the processing result of the METIS program is fed back to the FEEQS program; and in the step A4, the processing result of the METIS program is processed in the FEEQS program, and the processing result of the FEEQS program is returned to the step A2.

[0011] Further, the initialization iteration result is the processing result of the FEEQS program, and the processing result of the FEEQS program comprises the elongation ratio, the poloidal flux radial distribution, the magnetic surface axis position and the plasma current.

[0012] Further, the coupling iteration of the transport and the balance is performed according to the initialization iteration result and the control parameter, and the coupling iteration comprises the following steps: in the step B1, the current step number is compared with the total step number; if the current step number is less than or equal to the total step number, steps B2 to B5 are performed; if the current step number is less than or equal to the total step number, the processing result of the FEEQS program is output as the coupling simulation result; in the step B2, the METIS program is called to process the processing result of the FEEQS program, and the plasma current profile is output; in the step B3, the deviation of the plasma current from the expected value in the processing result of the FEEQS program is obtained, the deviation is fed back to the current of the central solenoid coil through a proportional-integral controller, and the current of the central solenoid coil is updated; in the step B4, the FEEQS program is called to process the plasma current profile and the updated current, and the processing result of the FEEQS program is obtained; and in the step B5, the current step number is increased by 1, and the processing result of the FEEQS program is returned to the step B1.

[0013] In a second aspect, a coupling simulation system for a tokamak is provided, which comprises: an initialization module configured to initialize a plurality of plasma parameters; an initialization iteration module configured to perform an initialization iteration according to the plurality of plasma parameters and output an initialization iteration result; a parameter setting module configured to set an iteration control parameter; the control parameter comprises a time step, a total step number and a current step number; and a coupling iteration module configured to perform a coupling iteration of the transport and the balance according to the initialization iteration result and the control parameter, and obtain a coupling simulation result.

[0014] Further, the coupling simulation system for the tokamak further comprises: a first data processing module configured to call the FEEQS program to process the plurality of plasma parameters to obtain a poloidal magnetic flux radial distribution, a flattening ratio, a poloidal magnetic flux radial distribution, and a magnetic surface axis position; a second data processing module configured to set a large radius, a small radius, a flattening ratio, and a Shafranov displacement in the METIS program, which are the same as the plurality of plasma parameters; and a third data processing module configured to edit a waveform of auxiliary heating power.

[0015] Further, the initialization iteration module comprises: a loop control unit configured to cyclically call the first data processing unit, the second data processing unit, the third data processing unit, and the fourth data processing unit to work until the poloidal magnetic flux radial distribution of the boundary is consistent with the poloidal magnetic flux radial distribution on the magnetic axis; the first data processing unit configured to call the FEEQS program to process the plurality of plasma parameters; the second data processing unit configured to input the processing result of the FEEQS program into the METIS program; the third data processing unit configured to process the processing result of the FEEQS program in the METIS program and feed back the processing result of the METIS program to the FEEQS program; and the fourth data processing unit configured to process the processing result of the METIS program in the FEEQS program and return the processing result of the FEEQS program to the second data processing unit.

[0016] Further, the coupling iteration module comprises: a numerical comparison unit configured to numerically compare the current step number with the total step number; a logic control unit configured to call the fifth data processing unit, the sixth data processing unit, the seventh data processing unit, and the eighth data processing unit to work when the current step number is less than or equal to the total step number; and a data output unit configured to work when the current step number is less than or equal to the total step number; the fifth data processing unit configured to call the METIS program to process the processing result of the FEEQS program and output a plasma current profile; the sixth data processing unit configured to obtain a deviation of the plasma current from an expected value in the processing result of the FEEQS program, feed back the deviation to a current of a central solenoid coil through a proportional-integral controller, and update the current of the central solenoid coil; the seventh data processing unit configured to call the FEEQS program to process the plasma current profile and the updated current to obtain the processing result of the FEEQS program; the eighth data processing unit configured to increase the current step number by 1 and return the processing result of the FEEQS program to the numerical comparison unit; and the data output unit configured to output the processing result of the FEEQS program as the coupling simulation result.

[0017] In a third aspect, the present application provides a computer device, comprising: a memory, a processor and a transceiver; the memory, the processor and the transceiver are connected in sequence in communication; the memory is used for storing a computer program, the transceiver is used for transmitting and receiving messages, and the processor is used for reading the computer program and executing the tokamak-oriented coupling simulation method as described in the first aspect or any possible design in the first aspect.

[0018] In a fourth aspect, the present application provides a computer readable storage medium, which stores instructions, when the instructions are run on a computer, execute the tokamak-oriented coupling simulation method as described in the first aspect or any possible design in the first aspect.

[0019] In a fifth aspect, the present application provides a computer program product comprising instructions, when the instructions are run on a computer, make the computer execute the tokamak-oriented coupling simulation method as described in the first aspect or any possible design in the first aspect.

[0020] Compared with the prior art, the present application has the following advantages and beneficial effects: on the one hand, by initializing a plurality of plasma parameters, the input quantity of the balance incoming transport includes not only the last closed flux surface LCFS of the poloidal magnetic flux, but also the elongation ratio, the large radius, the small radius, the Shafranov displacement and the plasma self-induction, so as to ensure the comprehensiveness of the exchange information; on the other hand, the magnetic field feedback control of the plasma exerted by the poloidal field coil is considered, and the control parameters including the time step, the total number of steps and the current number of steps are set, which not only ensures the stability of the plasma current, but also enables the coupling solution of the transport and the balance to be iterated self-consistently, so as to improve the accuracy of the simulation results. BRIEF DESCRIPTION OF DRAWINGS

[0021] In order to more clearly illustrate the technical solutions of the exemplary 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 considered as a limitation to the scope, and for those skilled in the art, other related drawings can also be obtained without creative labor.

[0022] Figure 1 A tokamak-oriented coupling simulation method flowchart provided for the embodiments of the present application;

[0023] Figure 2 A two-dimensional schematic diagram of the structure of a tokamak device provided for the embodiments of the present application;

[0024] Figure 3 A schematic diagram of the initial poloidal magnetic flux radial distribution provided for the embodiments of the present application;

[0025] Figure 4 The schematic diagram of the plasma current waveform provided for the embodiment of the present application

[0026] Figure 5 The schematic diagram of the central solenoid coil current waveform provided for the embodiment of the present application DETAILED DESCRIPTION

[0027] In order to make the objectives, technical solutions and advantages of the present application clearer, further detailed description will be made to the present application in combination with embodiments and drawings, and the schematic embodiments of the present application and the description thereof are only used for explaining the present application, but not for limiting the present application.

[0028] Embodiment: Current simulation technology has been able to better achieve the separate processing of transport and equilibrium solving, for example, CRONOS, TRANSP and METIS are common transport solving algorithms. In particular, METIS is a transport solver realized by MATLAB language, which has the advantage of less calculation time when solving the plasma core transport due to the use of a simplified transport model.

[0029] For equilibrium solving, common solving programs include EFIT, CEDRES++ and FEEQS, wherein EFIT solves equilibrium based on finite difference method; CEDRES++ is an equilibrium solver realized by C++ language; FEEQS is an equilibrium solving program based on finite element method, which not only has good adaptability to the shape of the tokamak device as shown in the drawings, but also has the characteristics of high calculation precision. Meanwhile, FEEQS is realized by MATLAB language. FEEQS and METIS are both realized by MATLAB language, which is convenient for the coupled solving of transport and equilibrium. Figure 2

[0030] In a first aspect, the present embodiment proposes a tokamak-oriented coupled simulation method by means of the FEEQS program and the METIS program, and the implementation process of the tokamak-oriented coupled simulation method is as shown in Figure 1 The method comprises the following steps:

[0031] Step 1: initializing a plurality of plasma parameters.

[0032] In order to ensure the comprehensiveness of the exchange information during the simulation of tokamak plasma transport and equilibrium, the plurality of plasma parameters in step 1 includes major radius R, minor radius a, elongation ratio K, Shafranov displacement d and plasma current IP. In the present embodiment, the major radius R is set to 1.7919 m, the minor radius a is set to 0.617 m, the elongation ratio K is set to 1.464 m, the Shafranov displacement d is set to 0 m and the plasma current IP is set to 500 KA.

[0033] ​Step 2: Perform initialization iteration according to the plurality of plasma parameters, and output the initialization iteration result. Specifically, step 2 includes:

[0034] Step 2.1: Call the FEEQS program to process the plurality of plasma parameters described in step 1, and calculate the initial poloidal flux radial distribution as shown in formula (1) and the elongation ratio K, the poloidal flux radial distribution Psi and the magnetic surface axis position Raxe calculated by the FEEQS program under the magnetic surface coordinate. Figure 3

[0035] Step 2.2: Call the METIS program, and set the same plurality of plasma shape parameters as the plurality of plasma parameters provided in step 1 in the METIS program. That is, set the same major radius R, minor radius a, elongation ratio k and Shafranov displacement d in the METIS program.

[0036] Step 2.3: Edit the waveform of the auxiliary heating power.

[0037] Step 2.4: Perform steps 2.41 to 2.44 between the FEEQS program and the METIS program until the poloidal flux radial distribution Psi on the boundary and the poloidal flux radial distribution Psi on the magnetic axis are consistent.

[0038] Step 2.41: Call the FEEQS program, and use the FEEQS program to process the plurality of plasma parameters (major radius, minor radius, elongation ratio, Shafranov displacement and plasma current) described in step 1 at the starting time point.

[0039] Step 2.42: Input the processing result of the FEEQS program into the METIS program.

[0040] Step 2.43: Process the processing result of the FEEQS program in the METIS program, and feed back the processing result of the METIS program to the FEEQS program.

[0041] Step 2.44: Process the processing result of the METIS program in the FEEQS program, and return the processing result of the FEEQS program to step 2.42.

[0042] As can be seen from steps 2.41 to 2.44, step 2 is to realize the completion of the initialization iteration between the FEEQS program and the METIS program. That is, at the starting time point, the output of the FEEQS program is taken as the input of the METIS program; conversely, the output of the METIS program is taken as the input of the FEEQS program for multiple iterations until the poloidal flux value Psi on the boundary and the poloidal flux value Psi on the magnetic axis are consistent, and finally the initialization iteration result is output.

[0043] ​Step 3: Set the iteration control parameters. The control parameters include the time step △t, the total number of steps N, and the current step i. Initially, set the time step △t = 0.001 s, the total number of steps N = 50, and the current step i = 0.

[0044] Step 4: Perform coupled iteration of transport and equilibrium based on the initialization iteration results output in Step 2 and the control parameters provided in Step 3 to obtain the coupled simulation results. Specifically, the following steps are included:

[0045] Step 4.1: Numerically compare the current step i with the total number of steps N. If the current step i is less than or equal to the total number of steps N, execute Steps 4.2 to 4.5; if the current step i is less than the total number of steps N, output the processing results of the FEEQS program as the coupled simulation results.

[0046] According to Step 3, the initial current step i = 0; set the total number of steps N = 100, then the current step i is less than the total number of steps N, and Step 4.2 is executed.

[0047] Step 4.2: Call the METIS program to process the processing results of the FEEQS program and output the plasma current profile.

[0048] It should be noted that the plasma current profile is composed of two parts: P' and ff', both of which are functions of the magnetic surface coordinates and together determine the plasma current profile. Among them, In formula (1), is the normalized magnetic surface coordinate, is the first current profile with the normalized magnetic surface coordinate as the independent variable; In formula (2), is the second current profile with the normalized magnetic surface coordinate as the independent variable, and μ0 is the vacuum permeability constant, μ0 = 4π * 10 -7 .

[0049] In this step, the processing results of the FEEQS program are the initialization iteration results of Step 2, which specifically include the elongation ratio K, the radial distribution of the poloidal flux Psi, the magnetic surface axis position Raxe, and the plasma current Ip.

[0050] Step 4.3: Obtain the deviation of the plasma current from the expected value in the processing results of the FEEQS program, feed back the deviation to the current of the central solenoid coil through a proportional-integral controller, and update the current of the central solenoid coil.

[0051] Specifically, according to step 4.2, the processing result of the FEEQS program contains the plasma current Ip, and the deviation between the plasma current Ip and the preset expected value can be obtained by comparison. The deviation is fed back to the current Ics of the central solenoid coil through a proportional-integral controller, and the formula I CS = I CS_init + ctr_I CS (1) The current Ics is updated, and the current Ics of the central solenoid coil is locked to change only with the proportional-integral controller feedback value.

[0052] In formula (1), Ics is the current of the central solenoid coil, Ics_init is the initial current of the central solenoid coil, Ics_init = -19.7781 A, and ctr_Ics is the feedback current of the controller.

[0053] The feedback current ctr_Ics is obtained by formula In formula (2), K1 and K2 are preset control parameters, K1 = -0.033 and K2 = -10, Ip_ref is the expected plasma current, and Ip_ref = 500 KA.

[0054] Step 4.4: The first current profile P', the second current profile ff', and the updated current Ics are processed by the FEEQS program to obtain the processing result of the FEEQS program.

[0055] Step 4.5: The current step number i is executed as i = i + 1, and the processing result of the FEEQS program is returned to the step 4.1.

[0056] When the coupling iteration is completed, the changes of the current of each coil with time and the change of the plasma current Ip with time can be obtained, as shown in Figure 4 and Figure 5

[0057] Corresponding to the transport and balance coupling simulation provided by the first aspect of the embodiment, the second aspect of the embodiment provides a coupling simulation system for a tokamak, comprising: an initialization module configured to initialize a plurality of plasma parameters; an initialization iteration module configured to perform initialization iteration according to the plurality of plasma parameters and output an initialization iteration result; a parameter setting module configured to set iteration control parameters; the control parameters include: a time step, a total step number, and a current step number; and a coupling iteration module configured to perform coupling iteration on transport and balance according to the initialization iteration result and the control parameters to obtain a coupling simulation result.

[0058] ​Further, the coupling simulation system for the tokamak further comprises: a first data processing module configured to call the FEEQS program to process the plurality of plasma parameters to obtain a poloidal magnetic flux radial distribution, a flattening ratio, a poloidal magnetic flux radial distribution, and a magnetic surface axis position; a second data processing module configured to set a large radius, a small radius, a flattening ratio, and a Shafranov displacement in the METIS program, which are the same as the plurality of plasma parameters; and a third data processing module configured to edit a waveform of auxiliary heating power.

[0059] Further, the initialization iteration module comprises: a loop control unit configured to cyclically call the first data processing unit, the second data processing unit, the third data processing unit, and the fourth data processing unit to work until the poloidal magnetic flux radial distribution of the boundary is consistent with the poloidal magnetic flux radial distribution on the magnetic axis; the first data processing unit configured to call the FEEQS program to process the plurality of plasma parameters; the second data processing unit configured to input the processing result of the FEEQS program into the METIS program; the third data processing unit configured to process the processing result of the FEEQS program in the METIS program, and feed back the processing result of the METIS program to the FEEQS program; and the fourth data processing unit configured to process the processing result of the METIS program in the FEEQS program, and return the processing result of the FEEQS program to the second data processing unit.

[0060] Further, the coupling iteration module comprises: a numerical comparison unit configured to numerically compare the current step number with the total step number; a logic control unit configured to call the fifth data processing unit, the sixth data processing unit, the seventh data processing unit, and the eighth data processing unit to work when the current step number is less than or equal to the total step number; and a data output unit configured to work when the current step number is less than or equal to the total step number; the fifth data processing unit configured to call the METIS program to process the processing result of the FEEQS program, and output a plasma current profile; the sixth data processing unit configured to obtain a deviation of the plasma current from an expected value in the processing result of the FEEQS program, feed back the deviation to a current of the central solenoid coil through a proportional-integral controller, and update the current of the central solenoid coil; the seventh data processing unit configured to call the FEEQS program to process the plasma current profile and the updated current to obtain the processing result of the FEEQS program; the eighth data processing unit configured to increase the current step number by 1, and return the processing result of the FEEQS program to the numerical comparison unit; and the data output unit configured to output the processing result of the FEEQS program as the coupling simulation result.

[0061] The third aspect of the embodiment provides a computer device for performing the tokamak-oriented coupling simulation method according to the first aspect or any possible design scheme in the first aspect, which comprises a memory, a processor and a transceiver; the memory, the processor and the transceiver are sequentially connected in communication; the memory is configured to store a computer program, the transceiver is configured to transmit and receive messages, and the processor is configured to read the computer program and perform the tokamak-oriented coupling simulation method according to the first aspect or any possible design scheme in the first aspect. Specifically, the memory can include, but is not limited to, a random access memory (RAM), a read-only memory (ROM), a flash memory, a first-in first-out memory (FIFO) and / or a first-in last-out memory (FILO), etc.; the processor can be, but is not limited to, a microprocessor with a model number of STM32F105 series. In addition, the computer device can further include, but is not limited to, a power module, a display screen and other necessary components.

[0062] The working process, working details and technical effects of the aforementioned computer device provided by the third aspect of the embodiment can be referred to the tokamak-oriented coupling simulation method according to the first aspect or any possible design scheme in the first aspect, which will not be described here.

[0063] The fourth aspect of the embodiment provides a computer readable storage medium storing instructions of the tokamak-oriented coupling simulation method according to the first aspect or any possible design scheme in the first aspect, that is, the computer readable storage medium stores instructions, when the instructions run on a computer, the tokamak-oriented coupling simulation method according to the first aspect or any possible design scheme in the first aspect is performed. Wherein, the computer readable storage medium refers to a carrier storing data, which can include, but is not limited to, floppy disks, optical discs, hard disks, flash memories, USB flash drives and / or memory sticks, etc. The computer can be a general-purpose computer, a special-purpose computer, a computer network or other programmable devices.

[0064] The working process, working details and technical effects of the aforementioned computer readable storage medium provided by the fourth aspect of the embodiment can be referred to the tokamak-oriented coupling simulation method according to the first aspect or any possible design scheme in the first aspect, which will not be described here.

[0065] The fifth aspect of the embodiment provides a computer program product comprising instructions which, when executed on a computer, cause the computer to carry out the method of simulation of coupling to a tokamak as described in the first aspect or any possible design of the first aspect. The computer can be a general purpose computer, a special purpose computer, a computer network or other programmable apparatus.

[0066] The above detailed description merely describes the specific implementation of the present application. It is to be understood that the above description only explains the purpose of the present application, the technical solutions and the beneficial effects, and should be understood that the above description is only the specific implementation of the present application and is not used to limit the protection scope of the present application. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present application shall be included in the protection scope of the present application.

Claims

1. A coupling simulation method for a tokamak, characterized by, The method comprises the following steps: initializing a plurality of plasma parameters; performing an initialization iteration according to the plurality of plasma parameters, and outputting an initialization iteration result; setting an iteration control parameter; the control parameter comprises a time step, a total step number and a current step number; performing a coupling iteration of transport and balance according to the initialization iteration result and the control parameter, and obtaining a coupling simulation result; the plurality of plasma parameters comprise a major radius, a minor radius, an elongation ratio, a Shafranov displacement and a plasma current; before performing the initialization iteration according to the plurality of plasma parameters, the following steps are included: calling an FEEQS program to process the plurality of plasma parameters, and obtaining a poloidal flux radial distribution and the elongation ratio, the poloidal flux radial distribution and the position of the magnetic surface axis under the magnetic surface coordinate; setting the major radius, the minor radius, the elongation ratio and the Shafranov displacement in the METIS program, which are the same as the plurality of plasma parameters; editing a waveform of auxiliary heating power; performing the initialization iteration according to the plurality of plasma parameters comprises the following steps: performing steps A1 to A4 between the FEEQS program and the METIS program until the poloidal flux radial distribution of the boundary is consistent with the poloidal flux radial distribution on the magnetic axis; step A1: calling the FEEQS program to process the plurality of plasma parameters; step A2: inputting the processing result of the FEEQS program into the METIS program; step A3: processing the processing result of the FEEQS program in the METIS program, and feeding back the processing result of the METIS program to the FEEQS program; step A4: processing the processing result of the METIS program in the FEEQS program, and returning the processing result of the FEEQS program to the step A2; the initialization iteration result is the processing result of the FEEQS program; the processing result of the FEEQS program comprises the elongation ratio, the poloidal flux radial distribution, the position of the magnetic surface axis and the plasma current; performing the coupling iteration of transport and balance according to the initialization iteration result and the control parameter comprises the following steps: step B1: performing a numerical comparison between the current step number and the total step number; if the current step number is less than or equal to the total step number, performing steps B2 to B5; if the current step number is less than or equal to the total step number, taking the processing result of the FEEQS program as the coupling simulation result and outputting the coupling simulation result; step B2: calling the METIS program to process the processing result of the FEEQS program, and outputting a plasma current profile; step B3: obtaining a deviation of the plasma current in the processing result of the FEEQS program from an expected value, feeding back the deviation to the current of the central solenoid coil through a proportional-integral controller, and updating the current of the central solenoid coil; step B4: calling the FEEQS program to process the plasma current profile and the updated current, and obtaining the processing result of the FEEQS program; Step B5: increment the current step number by 1, and return the processing result of the FEEQS program to the step B1.

2. A coupling simulation system for a tokamak, characterized by, Comprise: An initialization module for initializing a plurality of plasma parameters; An initialization iteration module for performing an initialization iteration according to the plurality of plasma parameters, and outputting an initialization iteration result; A parameter setting module for setting an iteration control parameter; The control parameter comprises: a time step, a total step number, and a current step number; A coupling iteration module for performing a coupling iteration of transport and equilibrium according to the initialization iteration result and the control parameter, and obtaining a coupling simulation result; The plurality of plasma parameters comprises: a major radius, a minor radius, an elongation ratio, a Shafranov shift, and a plasma current; The coupling simulation system for the tokamak further comprises: A first data processing module for calling a FEEQS program to process the plurality of plasma parameters, and obtaining a poloidal flux radial distribution, an elongation ratio under a magnetic surface coordinate, a poloidal flux radial distribution, and a magnetic surface axis position; A second data processing module for setting, in a METIS program, the same major radius, minor radius, elongation ratio, and Shafranov shift as the plurality of plasma parameters; A third data processing module for editing a waveform of auxiliary heating power; The initialization iteration module comprises: A loop control unit for cyclically calling a first data processing unit, a second data processing unit, a third data processing unit, and a fourth data processing unit to work until a poloidal flux radial distribution of a boundary is consistent with a poloidal flux radial distribution on a magnetic axis; The first data processing unit is configured to call the FEEQS program to process the plurality of plasma parameters; The second data processing unit is configured to input the processing result of the FEEQS program into the METIS program; The third data processing unit is configured to process the processing result of the FEEQS program in the METIS program, and feed back the processing result of the METIS program to the FEEQS program; The fourth data processing unit is configured to process the processing result of the METIS program in the FEEQS program, and return the processing result of the FEEQS program to the second data processing unit; The initialization iteration result is the processing result of the FEEQS program; the processing result of the FEEQS program comprises: an elongation ratio, a poloidal flux radial distribution, a magnetic surface axis position, and a plasma current; The coupling iteration module comprises: A numerical comparison unit for numerically comparing the current step number with the total step number; A logic control unit for calling a fifth data processing unit, a sixth data processing unit, a seventh data processing unit, and an eighth data processing unit to work when the current step number is less than or equal to the total step number; and calling a data output unit to work when the current step number is less than or equal to the total step number; The fifth data processing unit is configured to call the METIS program to process the processing result of the FEEQS program, and output a plasma current profile; A sixth data processing unit is configured to obtain a deviation of the plasma current in the processing result of the FEEQS program from an expected value, feed back the deviation to a current of the central solenoid coil through a proportional-integral controller, and update the current of the central solenoid coil; A seventh data processing unit is configured to call the FEEQS program to process the plasma current profile and the updated current, and obtain a processing result of the FEEQS program; An eighth data processing unit is configured to increase the current step number by 1, and return the processing result of the FEEQS program to the numerical comparison unit; A data output unit is configured to output the processing result of the FEEQS program as the coupling simulation result.

3. A computer device, comprising: Comprise: a memory, a processor and a transceiver; the memory, the processor and the transceiver are sequentially connected in communication; the memory is configured to store a computer program, the transceiver is configured to transceive messages, and the processor is configured to read the computer program and execute the tokamak-oriented coupling simulation method according to claim 1.

4. A computer-readable storage medium, characterized in that, The computer readable storage medium has instructions stored thereon, and when the instructions run on the computer, the tokamak-oriented coupling simulation method according to claim 1 is executed.

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