75 results about "Stellarator" patented technology

The invention discloses a coil connecting device for a star imitator magnet and the star imitator magnet, the coil connecting device comprises a shell, a first connecting part and a second connecting part, and a movable space is formed between the outer peripheral surface of each connecting part and the inner wall surface of an accommodating space and between the outer peripheral surface of each connecting part and a connecting hole. The first part of the first connecting part and the second connecting part can relatively rotate around the axial direction of the shell, so that the first connecting part and the second connecting part have a certain degree of freedom of movement in the radial direction of the shell and can adapt to irregular changes of adjacent surfaces of adjacent coils in the radial direction; and the risks of plastic deformation, fatigue cracks and fracture of the connecting part can be reduced.

The invention provides a multi-objective optimization method for non-planar coils of a star simulator and a star simulator magnet. The optimization method comprises the following steps: obtaining initial structures of a plurality of non-planar superconducting coils according to magnetic field configuration data of target plasma; according to the target magnetic field parameter, the engineering constraint parameter and the material constraint parameter of the configuration data, an objective function is constructed, the engineering constraint parameter comprises the engineering limit geometric parameter of the non-planar superconducting coil, and the material constraint parameter comprises the limit current carrying of the non-planar superconducting coil material; carrying out minimization solution on the target function to obtain optimized coil data; and performing materialization processing on the plurality of non-planar superconducting coils according to the optimized coil data to obtain a plurality of optimized non-planar superconducting coil models. According to the optimization method, a magnetic field matching-engineering feasibility-material safety three-dimensional constraint system is constructed, and the problem that the engineering cannot be realized on the ground is avoided.

The invention provides a method and a system for measuring plasma current in a quasi-ring symmetrical star simulator, and relates to the technical field of star simulators, and the method comprises the steps: determining a sensor design index according to a bootstrap current simulation calculation result, and converting the design index into an actual arrangement scheme according to an installation environment constraint; all the magnet coils are independently excited in a plasma-free state, wall eddy current interference signals generated by the magnet coils are calibrated, and thus wall eddy current calibration voltage signals are output; a sensor in an actual arrangement scheme is used for synchronously collecting a total original induced voltage signal including plasma current and wall eddy current; an integral voltage signal representing the total current is output; and compensating the integral voltage signal by using the wall eddy current calibration voltage signal, and inverting the final measurement value of the plasma current in the quasi-ring symmetric star simulator. The device and the method have the beneficial effects that the interference of a stray field on a measurement result is weakened, and a high-precision diagnostic tool is provided for the plasma physical research of the star simulator.

The invention provides a thermal radiation shielding assembly and a thermal radiation shielding system of a star imitator, the thermal radiation shielding assembly comprises a plasma container and a Dewar tank surrounding the periphery of the plasma container, and a first thermal radiation shielding part is arranged in an annular cavity formed between the plasma container and the Dewar tank; the first heat radiation shielding part is fixedly arranged on the periphery of the plasma container in a surrounding mode and comprises a cold pipe assembly, a first heat insulation assembly, a first cold shield assembly and a first supporting assembly; the cooling pipe assembly comprises a cooling pipe which surrounds and is attached to the peripheral wall of the plasma container to extend; the first heat insulation assembly extends around the plasma container, and the inner side surface of the first heat insulation assembly is attached to the peripheral wall of the cooling pipe assembly. The first cold shield assembly and the first heat insulation assembly extend around the plasma container at an interval; the first cold shield assembly is fixed to the outer wall of the plasma container through the first supporting assembly to form multiple heat radiation shielding layers, and high-temperature heat radiation from the plasma container can be isolated.

The present disclosure is directed to stellarators or assemblies including a stellarator including removable and / or replaceable components, such as removable field shaping units and / or removable shaping coils. In some embodiments, the stellarators of the present disclosure include a toroidal sector, which includes one or more removable field shaping units.

The invention provides a diagnosis method and system suitable for magnet current in a quasi-ring symmetrical star simulator, and relates to the technical field of star simulators, and the method comprises the steps: setting a target voltage range, and finally outputting the mutual inductance coefficient, total number of turns and sectional area parameters of a coil; utilizing an electromagnetic induction conversion algorithm to generate an original measurement signal; an original measurement signal is input into an integrator through a shielded wire to obtain a proportional voltage which is strictly proportional to the current, and the proportional voltage is transmitted to a data acquisition interface; performing analog-to-digital conversion on the proportional voltage received by the acquisition interface to generate a discrete sequence, calculating a conversion coefficient by combining a target mutual inductance coefficient and a fixed time constant, and finally restoring a digital current signal; and inputting the digital current signal to an upper computer to realize dynamic waveform display, and outputting key boundary parameters to a plasma experiment module. The method has the advantages that the method can adapt to complex changes of magnet current, and enough measurement precision and response speed can be provided in a low-parameter experiment.

Disclosed herein are methods, systems, media, and techniques for training machine learning models to generate nuclear fusion reactor configurations. Further disclosed herein are systems, methods, computer-readable media, and techniques for configuring a stellarator, including: (a) obtaining one or more parameters of a target stellarator; (b) generating a plurality of target stellarator approximations based at least in part on the one or more parameters of the target stellarator, wherein at least a subset of the plurality target stellarator approximations: (i) have a toroidal profile, and (ii) comprise a plurality of concentric toroids; and (c) presenting at a graphical user interface a representation of the plurality of target stellarator approximations.

The invention provides a diagnosis method and system for plasma energy storage in a quasi-ring symmetric star simulator, and relates to the technical field of star simulators, and the method comprises the steps: adjusting a temperature drift resistor of a diamagnetic differential integrator, executing a quasi-ring symmetric configuration vacuum field magnet coil power-on test according to a general discharge waveform, and completing the calibration of the diamagnetic differential integrator; respectively measuring and calculating the compensation coefficient of each magnet coil; carrying out a power-on experiment with the same coil configuration parameters in the plasma discharge experiment of the quasi-ring symmetric star simulator test device under a vacuum condition to obtain wall eddy current stray field data under a corresponding condition; the real diamagnetic flux in the plasma discharge experiment is calculated by combining the magnet coil compensation coefficient and the wall eddy stray field data; and real plasma energy storage information in plasma discharge is obtained through calculation. The device has the beneficial effects that the measurement precision of the plasma energy storage signal in the star simulator device is improved, and experimental data support is provided for the physical research of the plasma of the star simulator.

A computer-implemented method is disclosed for designing magnetic field geometries in magnetically confined plasmas, such as stellarators, to minimize energy or particle transport due to plasma turbulence. The method utilizes machine learning (ML) models trained on datasets of gyrokinetic simulations. These models predict turbulent transport based on geometric features derived from the magnetic configuration, which influence solutions of the gyrokinetic equation in ballooning representation. The input features include both raw geometrical quantities-such as field strength, curvature drifts, and perpendicular wavenumbers-and engineered features derived therefrom. The models may incorporate translational invariance and be implemented as convolutional neural networks or via solutions to parameterized differential equations. The resulting ML-driven target functions are computationally efficient and suitable for use in optimization algorithms to identify magnetic geometries that enhance plasma confinement.

A computer-implemented method is disclosed for designing magnetic field geometries in magnetically confined plasmas, such as stellarators, to minimize energy or particle transport due to plasma turbulence. The method utilizes machine learning (ML) models trained on datasets of gyrokinetic simulations. These models predict turbulent transport based on geometric features derived from the magnetic configuration, which influence solutions of the gyrokinetic equation in ballooning representation. The input features include both raw geometrical quantities—such as field strength, curvature drifts, and perpendicular wavenumbers—and engineered features derived therefrom. The models may incorporate translational invariance and be implemented as convolutional neural networks or via solutions to parameterized differential equations. The resulting ML-driven target functions are computationally efficient and suitable for use in optimization algorithms to identify magnetic geometries that enhance plasma confinement.

The invention provides a supporting device for a non-planar star simulator coil, the supporting device comprises a base and a plurality of supporting assemblies arranged at intervals in the circumferential direction of the base, and each supporting assembly comprises a height adjusting part, an angle adjusting part and a mounting part, one end of the height adjusting part along the height direction is connected with the corresponding position of the base, the other end is connected with the mounting part through the angle adjusting part, the mounting part is provided with a mounting groove, and the side wall of the corresponding position of the coil is embedded in the mounting groove. According to the supporting device, the height of the mounting part relative to the base is adjusted through the height adjusting part, and the inclination angle of the mounting part relative to the height direction is adjusted through the angle adjusting part, so that the corresponding position of the coil can be embedded into the mounting groove of the mounting part in a matched manner; particularly, when the supporting device supports the non-planar annular coil, the shape of the coil does not deform, and the production precision of the coil is improved.

Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.

A stellarator comprising a non-planar magnetic field coil with a cable as well as a method for providing a cable for a non-planar magnetic field coil in a stellarator is presented. Additionally, a cable and a method for manufacturing a cable are presented. The cable comprises an inner section (100) comprising multiple layers of superconductor material (200), the multiple layers of superconductor material (200) having a first orientation (210, 210a, 210b, 210c), an outer section (300) surrounding the inner section (100), the outer section (300) having a cross-section (310) with a second orientation (320, 320a, 320b, 320c), wherein the outer section (300) comprises a first conductive material (410) which fixes the first orientation (210, 210a, 210b, 210c), wherein the first orientation (210, 210a, 210b, 210c) changes along a length (50) of the cable (40) with respect to the second orientation (320, 320a, 320b, 320c).

The application provides a stress analysis method suitable for a superconducting magnet winding of a stellarator, comprising: building a finite element model of the superconducting magnet of the stellarator; performing multi-physical field coupling on the finite element model, and performing cutting processing on the coupled finite element model to cut a local region from the finite element model as a cutting block; re-performing multi-physical field coupling on the cutting-processed finite element model to obtain a global model; performing detailed modeling on the winding and the filling layer corresponding to the cutting block to obtain a detailed model; mapping the deformation displacement of the cutting block corresponding to the global model to the detailed model; and solving the displacement-mapped detailed model to determine stress data corresponding to the cutting block. The application can quickly and accurately evaluate the stress of the winding by locally and in detail modeling the cutting block, combining the global model and the local model, and through the displacement mapping method.

A stellarator comprising a non-planar magnetic field coil with a cable as well as a method for providing a cable for a non-planar magnetic field coil in a stellarator is presented. The cable comprises an inner section (100) comprising multiple layers of superconductor material (200), the multiple layers of superconductor material (200) having a first orientation (210, 210a, 210b, 210c), an outer section (300) surrounding the inner section (100), the outer section (300) having a cross-section (310) with a second orientation (320, 320a, 320b, 320c), wherein the outer section (300) comprises a first conductive material (410) which fixes the first orientation (210, 210a, 210b, 210c), wherein the first orientation (210, 210a, 210b, 210c) changes along a length (50) of the cable (40) with respect to the second orientation (320, 320a, 320b, 320c).

The application discloses a kind of nuclear fusion adaptive control system and method based on reinforcement learning, the control system includes physical layer and control layer, physical layer contains tokamak / stellarator device, Thomson scattering and so on diagnostic system and FPAD / PAM projectile injection system, responsible for collecting plasma density profile, temperature profile and other data and executing fuel supply;Control layer is reinforcement learning intelligent agent, contains state perception, strategy network and execution interface module, strategy network uses PPO / SAC algorithm, state perception is included line average density, density change rate and historical sequence data;The control method is trained offline by Torax simulator, is optimized by composite reward function, forms perception-decision-making-execution-feedback closed-loop control, supports real machine deployment and online fine tuning.The application solves the problem of traditional PID control lag, adaptive difference, the control precision is improved by about 40%, density fluctuation is reduced by about 50%, prolongs hardware maintenance cycle, adapts nuclear fusion long pulse operation demand.

The invention discloses an ultra-low temperature vacuum system of a Tokamak or star imitator adaptive to nuclear fusion, and relates to the technical field of nuclear fusion equipment, the ultra-low temperature vacuum system comprises a vacuum chamber, a plasma state sensor is embedded in the inner wall of the vacuum chamber, the outer end of the vacuum chamber is provided with a sealing interface, the outer end of the sealing interface is provided with a primary filter, and the primary filter is provided with a secondary filter. A getter bin is installed at the outer end of the primary filter, an auxiliary pump is installed at the outer end of the getter bin, a stop valve is installed at the outer end of the auxiliary pump, a cold trap is installed at the outer end of the stop valve, the side wall of the cold trap is connected with a refrigerating machine through a pipeline, and a main pump is installed at the outer end of the cold trap. By arranging a series of structures, the pain point of decoupling of a traditional system and plasma operation is thoroughly solved, all the components cooperate to guarantee the ultrahigh vacuum environment, interference of impurity gas on plasma constraint is greatly reduced, and the stability and success rate of a nuclear fusion experiment are remarkably improved.

This invention provides a winding fixture for a stellarator coil, comprising a winding mold and a radial adjustment component. The winding mold includes an annular support base, an inner side plate, and an outer side plate. The inner and outer side plates are spaced apart along the radial direction of the support base and are fixed to the top of the support base. The inner side plate has multiple connecting portions spaced apart along its circumference, each connecting portion including multiple first threaded through holes spaced apart along the axial direction of the inner side plate. The radial adjustment component is inserted into one of the first threaded through holes of a corresponding connecting portion and threadedly connected to the first threaded through hole. The end face of the radial adjustment component near the outer side plate abuts against the inner surface of the outer side plate or the inner surface of the already wound conductor. By cooperating with the multiple rows of first threaded through holes in the circumference and axial direction of the inner side plate and the radial adjustment component, the radial dimension of the winding can be precisely adjusted, achieving accurate radial positioning of the coil, improving the coil forming quality and magnetic field configuration accuracy, and enhancing the overall performance of the stellarator device.

A stellarator with a non-planar magnetic field coil with a first plate as well as a method of winding a non-planar magnetic field coil for a stellarator is presented. The first plate (100) comprises a first surface (110) with a non-planar geometry and a first recess (120). The first recess (120) extends along a first path (130) along the first surface (110). The first recess (120) has a first cross-section (140).

This invention discloses a coil support device for a stellarator magnet and a stellarator magnet. The coil support device includes a first sliding component and a second sliding component. When applied to a stellarator magnet, the sliding end of the first sliding component can slide relative to the fixed end in a first direction within a first displacement threshold range, and the sliding end of the second sliding component can slide relative to the fixed end in a second direction within a second displacement threshold range. This provides the coil with multiple degrees of freedom in various directions, facilitating assembly and absorbing the multi-directional deformation generated during stellarator magnet operation, avoiding unidirectional stress concentration and thus reducing the risk of stress concentration in the stellarator as a whole. Furthermore, the coil support device is equipped with a heat insulation component, which blocks the longitudinal heat transfer path from the high-temperature environment to the support structure. Therefore, the coil support device provided by this invention can both compensate for magnet displacement and provide thermal isolation through the heat insulation component.

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.

The present disclosure relates to a stellarator (1) comprising: a plurality of non-planar, superconducting coils, for generating a magnetic field for confining a plasma inside a plasma vessel; and a coil support structure (30, 40, 50) comprising: a first structural arrangement (30) arranged between a center (20) of the stellarator and the plasma vessel and configured to balance a radial force exerted by the magnetic field on the plurality of coils; a second structural arrangement (40, 50) configured to balance local forces exerted by the magnetic field on one or more coil segments of the plurality of coils; wherein the local forces cause at least a toroidal motion and / or a toroidal deformation of the one or more segments of the plurality of coils.

A breeder blanket is disposed within a stellarator. The breeder blanket defines a breeder zone through which a particle and a flow gas flows. The particle interacts with a neutron generated by a fusion reaction within the stellarator to generate heat. The flow gas absorbs the heat. A separator at an outlet of the breeder blanket separates the flow gas from the particle. The heat in the flow gas is used to generate power.

The invention discloses a superconducting magnet inner joint structure suitable for a star simulator and a use method thereof, and relates to the technical field of superconducting cables, the structure comprises a shell, at least two superconducting conductors and a crimping assembly, a protection chamber is formed in the shell, and two ends of the shell are provided with sealing ports. A metal stable layer at a connecting end, extending into a protection cavity, of a superconducting conductor is removed to form an exposed superconducting layer window, and then pressure is applied to the connecting end through a crimping assembly arranged on a shell, so that superconducting layers in the superconducting layer windows of different superconducting conductors are in direct physical contact in the protection cavity and form electric connection; the metal stable layer at the connecting end is removed, so that the current does not need to be transmitted through the metal stable layer with high conductivity, but is directly conducted through the superconducting layer in the superconducting layer window, the generation of Joule heat is avoided, and the advantage of low loss of the superconducting material is fully exerted.

A stellarator, comprising a non-planar magnetic field coil including at least one winding of a high temperature superconductor, HTS, cable (500), the HTS cable (500) comprising in a first cross-section (530): - first multiple layers of superconductor material (100) with: a first geometric orientation (110, 111), a first magnetic orientation (120), and a first angle (310) between the first geometric orientation (110) and the first magnetic orientation (120); - second multiple layers of superconductor material (200) with: a second geometric orientation (210, 211), a second magnetic orientation (220), and a second angle (320) between the second geometric orientation (210) and the second magnetic orientation (220); with a third angle (330) between the first magnetic orientation (120) and the second magnetic orientation (220), wherein the third angle (330) is larger or smaller than o°.

The invention provides a magnetic field configuration tracing imaging system and method of a star simulator. The magnetic field configuration tracing imaging system comprises an electron beam emission regulation and control unit, a dynamic fluorescence imaging unit and an image acquisition unit, the electron beam emission regulation and control unit is used for emitting electron beams in the three-dimensional vacuum magnetic field; the dynamic fluorescence imaging unit comprises a fluorescence grid mesh arranged at a selected Poincare section of the three-dimensional vacuum magnetic field, and a grid mesh driving mechanism for driving the fluorescence grid mesh to perform periodic reciprocating motion; and the image acquisition unit is used for imaging the fluorescent grid mesh. According to the invention, the fluorescent grid mesh is creatively enabled to do periodic reciprocating motion and is matched with the image acquisition unit, so that not only can the magnetic field configuration measurement of the three-dimensional vacuum magnetic field be realized, but also the inherent imaging blind area of the static grid mesh is eliminated, and thus more accurate and continuous magnetic surface track images can be obtained; and more reliable support is provided for accurately verifying the magnetic field configuration of the three-dimensional vacuum magnetic field of the star simulator.

The application provides a kind of quasi-ring symmetry star simulator plasma current measurement method and system, it is related to star simulator technical field, including determining sensor design index according to bootstrap current simulation calculation result, and actual arrangement scheme is converted into design index according to installation environment constraint;In the state of no plasma, all magnet coils are excited separately, and the wall eddy current interference signal generated by the magnet coil is calibrated, so as to output the wall eddy current calibration voltage signal;The total original induction voltage signal including plasma current and wall eddy current is synchronously collected by using the sensor in the actual arrangement scheme;Output integral voltage signal representing total current;The integral voltage signal is compensated by using the wall eddy current calibration voltage signal, and the final measurement value of quasi-ring symmetry star simulator plasma current is inverted.The beneficial effects of the application are to weaken the interference of stray field on the measurement results, and to provide a high-precision diagnostic tool for star simulator plasma physics research.

Disclosed herein are methods, systems, media, and techniques for training machine learning models to generate nuclear fusion reactor configurations. Further disclosed herein are systems, methods, computer-readable media, and techniques for configuring a stellarator, including: (a) obtaining one or more parameters of a target stellarator; (b) generating a plurality of target stellarator approximations based at least in part on the one or more parameters of the target stellarator, wherein at least a subset of the plurality target stellarator approximations: (i) have a toroidal profile, and (ii) comprise a plurality of concentric toroids; and (c) presenting at a graphical user interface a representation of the plurality of target stellarator approximations.

The application discloses a coil unit for a stellarator magnet, a coil module and the stellarator magnet. The coil unit comprises a first special-shaped coil and a second special-shaped coil which are oppositely arranged along the axial direction of the coil unit, a flexible connecting assembly and a rigid connecting assembly are arranged between the first special-shaped coil and the second special-shaped coil, and the coil unit is supported by a flexible supporting assembly. In this way, the first special-shaped coil and the second special-shaped coil are connected by the flexible connecting assembly and the rigid connecting assembly at the same time, the rigid connecting assembly can provide structural support for the two coils, the flexible connecting assembly can adapt to the deformation of the two coils, and the flexible supporting assembly can enable the coil unit to move in the radial direction of the coil unit relative to a central connecting component. When applied to the stellarator magnet, the coil unit can compensate in multiple degrees of freedom, so that the stellarator magnet can simultaneously have the advantages of reliable support and deformation adaptation.