134 results about "Tokamak" patented technology

The invention relates to the technical field of Tokamak nuclear fusion, and discloses an assembling method of a pre-assembled assembly of a nuclear fusion device and an installing method of the nuclear fusion device. The pre-assembled assembly comprises a vacuum chamber, a window neck tube in the vacuum chamber, a vacuum chamber cold shield and a TF magnet; the assembling method of the nuclear fusion device preassembled assembly comprises the following steps: supporting between a cold shield inner sector and a vacuum chamber through a first tool; a first tool is supported between the cold shield outer sector and the vacuum chamber; the TF magnet is connected with the middle window position of the vacuum chamber through a second tool, the upper arc-shaped section of the outer fan section of the cold shield is connected with the hoisting tool of the TF magnet through a third tool, and the lower window section of the outer fan section of the cold shield is connected with the second tool; and the middle window section and the annular field magnet supporting seat are connected through a fourth tool. According to the assembling method of the nuclear fusion device pre-assembled assembly, interference among installation of the vacuum chamber, the window neck tube in the vacuum chamber, the vacuum chamber cold shield and the TF magnet can be avoided, and the stability and functionality of the pre-assembled assembly structure are guaranteed.

Main characteristic of the invention is the exploitation of the very large flux of high energy neutrons generated in a nuclear fusion tokamak with beam-driven plasma for the purpose of producing radioisotopes. It specifically relates to the deployment of precursor materials into the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of Deuterium (D) and Tritium (T) to generate radioactive isotopes, so-called radioisotopes. The precursor materials contained in metallic capsules are incorporated into the blankets that surround the plasma.

The invention relates to the technical field of Tokamak plasma diagnosis and data fusion, in particular to a multi-modal fusion Tokamak high-frequency Thomson scattering reconstruction method. According to the technical scheme, the method comprises the following steps: acquiring multi-modal diagnosis data on a Tokamak device, wherein the multi-modal diagnosis data comprises high-frequency auxiliary diagnosis data and low-frequency Thomson scattering data; and performing feature engineering and physical enhancement processing on the high-frequency auxiliary diagnosis data. According to the method, through multi-modal diagnosis data fusion and interpretable KAN network modeling, the Thomson scattering time resolution is greatly improved on the premise that hardware is not transformed, and high-fidelity reconstruction of sub-millisecond transient processes such as ELM and magnetic island evolution is achieved; the method has physical interpretability, can reveal the implicit relationship between diagnostic quantities, enhances the robustness under complex experimental conditions through strategies such as modal loss, and provides key high-frequency diagnostic support for Tokamak high-performance operation and real-time control.

The invention provides a probe power supply over-current protection circuit and an over-current protection method thereof, relates to the technical field of power electronics, and solves the problems that periodic instantaneous over-current and continuous fault over-current are difficult to accurately distinguish and a control signal and a protection system lack a linkage mechanism in the prior art. In the circuit, a current detection unit generates a single over-current trigger signal when detecting a single over-current event; the central control unit sends a blocking signal after receiving the single overcurrent trigger signal, and sends a reset signal after preset time delay; meanwhile, cumulative counting is carried out on single overcurrent trigger signals, and whether an overcurrent fault occurs or not is judged according to a preset threshold number of times; the output control unit is used for controlling the closing and resetting of a probe power supply under the action of different signals; and the state feedback unit feeds back state information to the main control system when an overcurrent fault occurs. According to the invention, accurate response to the ELM overcurrent of the Tokamak device and reliable blocking of persistent faults are realized.

The invention discloses a Tokamak plasma multi-parameter cooperative configuration analysis method, and relates to the technical field of plasma multi-parameter cooperative configuration analysis, and the method comprises the following steps: constructing a parameter database to store plasma parameters; performing normalization processing on the plasma parameters to obtain normalized parameters of the plasma parameters; whether correlation exists between the two plasma parameters or not is analyzed, and an independent incidence relation is obtained; analyzing whether the plasma parameters are simultaneously influenced by more than two plasma parameters, and analyzing a comprehensive association relationship between the plasma parameters; when the configuration of the plasma is regulated and controlled, plasma parameters are cooperatively regulated and controlled based on the independent incidence relation and the comprehensive incidence relation; the plasma multi-parameter cooperative configuration analysis method is used for solving the problem that better cooperative control and analysis cannot be carried out on plasmas due to the fact that correlation analysis of different plasma parameters is not comprehensive enough in an existing plasma multi-parameter cooperative configuration analysis technology.

The invention discloses a multi-stage isolation high vacuum obtaining system of a neutral beam injection device and a control method, and relates to the field of nuclear fusion Tokamak vacuum pumping design. The low-temperature pump unit comprises a plug-in low-temperature pump in a neutral beam vacuum chamber, and the plug-in low-temperature pump is used for refrigerating and cooling liquid nitrogen and liquid helium to adsorb gas to realize vacuum pumping; the low-temperature pump preceding-stage air extractor unit comprises a molecular pump unit, a roots pump unit and a mechanical pump unit; an inlet of the molecular pump set is connected with the neutral beam vacuum chamber through a gate valve, and an outlet of the molecular pump set is connected with an inlet of the roots pump set through a forestage valve. An inlet of the roots pump set is connected with the neutral beam vacuum chamber through a preceding stage valve and a pre-pumping valve, and an outlet of the roots pump set is connected with the mechanical pump set through the preceding stage valve. By adopting a multi-stage vacuum shielding technology and a step-by-step start-stop strategy, step-by-step transition from low vacuum to high vacuum and from high vacuum to low vacuum can be efficiently, stably and reliably realized, and an air extractor unit and a vacuum environment are protected from being polluted.

The invention relates to the technical field of nuclear fusion, and discloses an ultrasonic molecular beam injection system for a fusion device.The ultrasonic molecular beam injection system comprises a gas source, a pressurizing unit, a storage unit and an injection unit, the pressurizing unit comprises a gas conveying pipeline, and the two ends of the gas conveying pipeline communicate with the gas source and the storage unit correspondingly; a booster pump is arranged on the gas conveying pipeline and used for pressurizing gas in the direction away from the gas source, and the storage unit can receive and store the pressurized gas so that the gas can reach a preset pressure value; the injection unit comprises an injection pipeline and a nozzle, one end of the injection pipeline is communicated with the storage unit, the other end of the injection pipeline is provided with the nozzle, the nozzle is used for stretching into a Tokamak vacuum chamber of the fusion device, and the injection pipeline can convey gas in the storage unit to the nozzle so as to form an ultrasonic molecular beam current through the nozzle. According to the invention, the injection function of the ultrasonic molecular beam in a large fusion device can be realized.

The invention provides a design method and device for a biological shielding wall of a fusion device and electronic equipment. The design method of the biological shielding wall of the fusion device comprises the steps that a biological shielding occupying model is segmented in the height direction to obtain a plurality of biological shielding occupying modules, and the biological shielding occupying modules at least comprise top shielding modules used for arranging embedded parts; the bottom shielding module is used for arranging the bottom of the Tokamak Dewar base and an annular support; based on the performance indexes of the biological shielding wall, performing structural design on each biological shielding occupation module to obtain a biological shielding engineering module; and dividing each biological shielding engineering module in the circumferential direction to obtain a plurality of prefabricated sub-modules, and obtaining the biological shielding wall formed by splicing the plurality of prefabricated sub-modules. According to the method, on-site high-altitude, high-strength and long-time complex operation is reduced, the construction safety risk is reduced, and modular removal of the biological shielding wall and waste treatment are more efficient.

The invention discloses a Tokamak plasma magnetic response model construction method, a Tokamak plasma magnetic response model construction system and a medium. Relates to the technical field of nuclear fusion plasma simulation. According to the scheme, improvement is carried out on the basis of the prior art, modeling is carried out on the magnetic response of the Tokamak plasma on the basis of basic data of the Tokamak plasma, and plasma behaviors are directly learned from experimental data; the simulator taking the plasma magnetic configuration evolution autoregression model as a carrier can process nonlinear terms and high-order terms, and is low in calculation cost, high in speed and capable of being applied in real time; according to the method, the behavior of the plasma under magnetic control can be well simulated, the plasma behavior is directly learned from experimental data without simplifying and assuming plasma properties, and the method can be used for off-line simulation and can also be used for control strategy optimization or fault detection in real time.

The invention discloses a Tokamak plasma rupture prediction method based on cWGAN and TCN, which takes AUC as a measurement index to evaluate the effectiveness of a model, and adopts a conditional Wasserstein generative adversarial network (cWGAN)-based minority class sample generation method for solving the problem that the number of minority class samples is limited. Gradient penalty (GP) is introduced in a training stage to improve the quality of generated samples and training stability, and an inverse frequency mini-batch minority class equilibrium training strategy is adopted to enable a generator to fully learn distribution characteristics of broken samples, so that high-quality minority class samples are generated and a training set is expanded. A Transform structure is introduced on the basis of a time convolutional network (TCN), local time sequence features are efficiently extracted by using the TCN, and the Transform enhances the expression ability of a model for a long-time dependency relationship and global features, so that the prediction effect is improved.

The invention provides an assembly construction method of a biological shielding wall of a fusion device and the biological shielding wall. The assembly construction method of the biological shielding wall of the fusion device comprises the following steps: manufacturing a wall body framework of a prefabricated sub-module; the wall body frameworks of the prefabricated submodules are assembled in the circumferential direction to obtain an annular framework of the biological shielding wall module, and the biological shielding wall module at least comprises a top shielding module used for arranging embedded parts and a bottom shielding module used for arranging the bottom of a Tokamak Dewar base and an annular support; and the annular framework is hoisted to a pouring foundation, and the interior of the annular framework is poured after hoisting is completed every time. According to the method, on-site high-altitude, high-strength and long-time complex operation is reduced, and construction safety risks are reduced. In addition, if internal parts need to be replaced or overhauled in the future, corresponding structures on the specific prefabricated submodules can be directionally dismantled, and when the service life of the fusion device is over, modular dismantling of the biological shielding wall and waste treatment are more efficient.

The invention relates to the design, configuration and operation concept of a system, herein called radioisotope recovery system, to deploy and recover different precursor materials into and from the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of D and T ions, which will cause the generation of radioactive isotopes (also called radioisotopes). Main characteristics of the invention are (i) a closed loop that circulates precursor materials into and out of a nuclear fusion tokamak with beam-driven plasma, (ii) the compliance of the system with the design and maintenance of a nuclear fusion tokamak with beam-driven plasma.

The invention discloses a cantilever beam vibration absorber and a Tokamak device, and belongs to the field of vibration control. The cantilever beam vibration absorber comprises an acoustic black hole cantilever beam which comprises an acoustic black hole structure; the piezoelectric element is located on any surface of the acoustic black hole structure in the thickness direction; the piezoelectric shunt circuit is electrically connected with the piezoelectric element; the damping layer is located on at least one side of the acoustic black hole structure in the thickness direction; the tuned mass block is located on the side, away from the acoustic black hole structure, of the damping layer. Broadband vibration reduction can be achieved, the vibration reduction frequency is flexible, accurate and adjustable, and the vibration reduction effect is effectively improved.

This invention discloses a tokamak plasma turbulence prediction method and system based on layer-theoretic topology and spectral neural operators. The method includes acquiring diagnostic and control data from a tokamak device and converting them into a set of physical field vectors, actuator vectors, and equilibrium parameter vectors; mapping the physical field vector set to a latent grid representation and fusing the actuator and equilibrium parameter vectors to obtain a conditional latent grid representation; using a multi-layer Fourier neural operator for time evolution to obtain the latent grid representation for the next time step; applying multi-region consistency constraints to the latent grid representation using a constraint mapping operator and a glue loss function; and using the constrained predicted latent grid representation for prediction, outputting the hazard level and remaining time prediction values ​​of plasma turbulence. Simultaneously, a projection and repair module applies physical constraints to the restored physical field prediction representation to obtain a corrected physical field prediction representation. This invention improves the accuracy of the results.

The invention relates to the field of cooling systems, in particular to a cooling system for a Tokamak device and a control method.The cooling system comprises a cooling device, a first heat exchange module, a device to be subjected to heat exchange and a water quality treatment module, and the cooling device is suitable for cooling a refrigerant medium flowing through the cooling device; the first heat exchange module is internally provided with a first heat exchange flow channel and a second heat exchange flow channel which can selectively exchange heat with each other, the first heat exchange flow channel and the second heat exchange flow channel are suitable for circulating a refrigerant medium, the first heat exchange flow channel is communicated with the cooling device, the device to be subjected to heat exchange is suitable for being arranged in the Tokamak device, and the device to be subjected to heat exchange is selectively communicated with the second heat exchange flow channel; the water quality treatment module selectively communicates with the second heat exchange flow channel, the water quality treatment module and the second heat exchange flow channel form a treatment loop, the water quality treatment module is suitable for optimizing the water quality of the refrigerant medium flowing through the water quality treatment module, and the overall operation stability of the cooling system can be improved.

The present invention relates to the technical field of nuclear fusion tokamak control systems, and in particular to a plasma control system health assessment method based on a decision table and an analytic hierarchy process. The technical solution comprises the following steps: assessing the plasma control system health status based on a decision table; assessing the plasma control system health status based on an analytic hierarchy process; and combining a decision table-based system health assessment method with an analytic hierarchy process-based health assessment method to comprehensively assess the plasma control system health status. By combining the advantages of decision tables and the analytic hierarchy process, the present invention achieves real-time health assessment and precise fault diagnosis for complex distributed control systems, significantly improving the stability, reliability, and safety of the plasma control system and providing strong support for the efficient operation of the system.

The invention discloses an auxiliary coil positioning device, and belongs to the technical field of nuclear power assembly.The auxiliary coil positioning device is used for assembling a coil and a wire box in a Tokamak device, an assembling hanger of the auxiliary coil positioning device comprises a connecting assembly and a guiding and limiting assembly, and the connecting assembly comprises a hanging part and a mounting part which are connected; the mounting part is detachably hung on the outer edge of the wire groove, the mounting part is attached to the inner side wall of one side of the wire groove, the guiding and limiting assembly comprises a guiding part, a connecting part and a limiting part, the connecting part is mounted on the mounting part, and the guiding part and the limiting part are both connected with the mounting part. According to the coil auxiliary positioning device, the size of the limiting piece can be correspondingly adjusted according to the size error of the contact position of the coil and the guiding piece, so that when the coil has the size error, the assembling precision of the coil and the wire box is improved, the magnetic field precision of a Tokamak device is improved, and stable constraint of the Tokamak device on plasma is guaranteed.

The invention discloses a CuCrZrTa alloy wire with a nanometer oxide dispersion strengthening phase and a preparation method of the CuCrZrTa alloy wire. The CuCrZrTa alloy wire comprises, by weight, 0.6 wt%-1.0 wt% of Cr, 0.08 wt%-0.12 wt% of Zr, 0.03 wt%-0.08 wt% of Ta, 0.2 wt%-0.4 wt% of Y2O3, 0.005 wt%-0.02 wt% of B and the balance Cu, and the phase structure of the wire comprises a nanometer Cr precipitation phase, YTaO dispersion particles and a B segregation grain boundary. Through Ta-Y2O3 interlocking to inhibit coarsening, B grain boundary segregation to resist irradiation, low-temperature sintering is adopted to retain nanocrystals, and two-stage aging is adopted to accurately regulate and control precipitated phase distribution, so that the prepared wire has the characteristics of high strength, high conductivity and excellent irradiation resistance of a copper alloy wire; and the extreme working condition requirements of a Tokamak magnet winding (requiring high conductivity / radiation resistance) and a divertor cooling pipeline (requiring high temperature resistance / creep resistance) are met.

The application discloses a boundary plasma simulation method under a unit magnetic surface coordinate system and belongs to the technical field of magnetic confinement tokamak boundary plasma simulation. Firstly, a physical model is expressed by using a unit magnetic surface coordinate system, physical quantity and geometric effect are separated by using unitized base vectors, and singularity near an X point is avoided; secondly, a toroidal Fourier series representation is combined with difference along a magnetic field line, problem dimension is reduced, and numerical dissipation is reduced; thirdly, a generalized finite difference method and a transformed coordinate system are adopted to process the X point and adjacent points, and the X point can be directly contained in a grid; finally, a grid screening method is used to pre-calculate geometric quantities and difference coefficients under high-density grids, and the calculation precision of geometric effect is improved. The application can accurately simulate the influence of the X point on the stability of the boundary plasma, significantly reduces the consumption of computing resources, and improves the simulation efficiency and accuracy.

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 application discloses a kind of plasma posture control agent strategy model construction method, device and medium, by constructing tokamak simulation environment, the environmental configuration parameter of out-of-control scene under the control of PID controller is identified, and the training environment of configuration is obtained;Using reinforcement learning agent model to learn, generate current command;The state of control point at each time is calculated based on tokamak simulation environment;The action command obtained by the control point state at each time, current command and PID controller are input into reward function, and the environment reward is calculated;According to the environment reward, the control point state at each time and current command, reinforcement learning training is carried out, and the command strategy is updated;When reinforcement learning agent model meets convergence condition, output agent strategy model.The application scheme provides a kind of strategy model in nonlinear and complex dynamic environment to deal with the ability of large disturbance of transient state, guarantees the stability and safety of tokamak device.

A modular tokamak is disclosed. The modular tokamak according to the present invention may comprise a plurality of core chambers sequentially connected in the longitudinal direction and may also comprise extension chambers each connecting two adjacent core chambers.

The application discloses a tokamak discharge modeling system based on a bidirectional long short-term memory neural network, which is composed of multiple modules, and the modules are low-coupling functional units.The modules at least include a data transfer module, a Batch data access input module, a training self-defined parameter module, a bidirectional long short-term memory neural network modeling module and a data visualization module.The whole system architecture is mainly divided into two paths, namely data training and data modeling.Using the visualization technology, the tokamak discharge experiment personnel can refer to the discharge modeling results and visualize the model training process.The application can one-key type in the experiment proposal stage to model the whole process of the tokamak discharge curve in advance, so that the experiment personnel and the proposal design personnel can check the validity and rationality of the proposal.The application can also be used for assisting data discovery after the experiment.

The application discloses an electromagnetic emission armature recycler for a tokamak device. The recycler comprises a vacuum exhaust port, an armature inlet track, an armature recovery cavity, an armature transmission track, a spiral conveying rod, a driving motor, a recovery sand storage tank and a plurality of sealing devices. The vacuum exhaust port discharges air in the electromagnetic emission armature recycler. The sealing devices are arranged at each connection. One end of the armature inlet track is connected with the tokamak device to receive the armature, and the other end is connected with the armature recovery cavity. The armature recovery cavity is filled with buffer sand. One end of the armature transmission track is connected with the lower part of the armature recovery cavity, and the spiral conveying rod is arranged in the armature transmission track. One end of the spiral conveying rod is connected with the armature motor and rotates along with the driving motor to drive the mixed armature and buffer sand to move along the armature transmission track. The recovery sand storage tank is connected with the lower part of the other end of the armature transmission track to recover the armature and buffer sand. The armature can be efficiently recovered in a vacuum environment.

The application relates to a teaching laser speckle interferometry experimental device for measuring material micro-morphology, belonging to the technical field of real-time diagnosis of material morphology of a tokamak wall. The device comprises a laser, a beam expander, a collimating mirror, a sample holder, two groups of beam splitters, a piezoelectric phase-shifting mirror, an imaging lens, a CCD camera and an optical platform. The device has a simple structure, the sensitivity can be dynamically expanded and selected according to actual detection conditions, and speckle interference fringes are obtained by subtracting the intensity field distribution functions before and after the surface displacement or deformation of the measured object. Compared with traditional morphology detection methods, physical contact with the measured object is reduced, thereby avoiding secondary deformation of the measured object and causing system errors.

The application discloses a kind of particle evolution simulation methods based on multi-component plasma radiation effect in tokamak, belong to magnetic confinement controlled nuclear fusion technical field.Firstly, the evolution of impurity density distribution, electron density distribution and ion density distribution is calculated, then continuous radiation and linear radiation are calculated, and then a variety of plasma radiation is accurately added inside magnetic island.Calculating the magnetic field configuration under the plasma radiation correction, and continue to calculate the evolution of plasma total radiation and related parameters under advanced magnetic field configuration, so repeated calculation, achieve the simulation effect of long time evolution.The application realizes the calculation of impurity, electron and ion real-time dynamic distribution, and can also calculate the evolution of a variety of plasma radiation under real three-dimensional magnetic field configuration, and then obtain the plasma related parameter profile at any time;Meanwhile, the spatial distribution of plasma radiation and the situation of magnetohydrodynamic instability under advanced magnetic field configuration are more accurately described.

The invention discloses a Tokamak plasma fracture grading protection method and system, and the method achieves the combined prediction of the fracture occurrence probability and the hazard degrees of different hazard types through a multi-task deep learning model, can achieve the early warning of the fracture risk, and also can achieve the prediction of the hazard degrees of halo current, thermal load and escape current. Then, attribution analysis is carried out on the multi-modal diagnosis signals, key features in the multi-modal diagnosis signals are determined, then fracture inducements are determined based on the key features, and remaining time windows from the current time node to fracture occurrence are determined; in the stage of hierarchical protection decision making, in combination with reversibility determined based on fracture inducement, flow reduction stability determined based on the damage degree of each fracture damage type and flow reduction adequacy determined based on a remaining time window from a current time node to fracture occurrence, inhibition means with different intensities are constructed in a targeted manner, excessive response is avoided, and the reliability of the system is improved. Therefore, the operation efficiency of the Tokamak device is maintained to the maximum extent.

A magnetic field sensor for use in a tokamak power plant is disclosed. The sensor comprises a Hall sensor 4 made of a radiation-hard semiconductor such as diamond or silicon carbide with a doped regio

The invention discloses a Tokamak plasma feedback control system and method based on real-time calculation of a helium-deuterium ratio, and the system consists of an automatic spectrum collection module, a real-time calculation module of the helium-deuterium ratio, and a data transmission and feedback control module. And continuous framing acquisition of emission spectrum signals including helium spectral lines and deuterium spectral lines in the whole discharge process is realized. And a helium-deuterium ratio real-time calculation algorithm is embedded, smooth filtering, baseline correction and numerical integration are carried out on a preset helium and deuterium characteristic spectral line narrow wavelength window in each frame of spectrum, corresponding spectral line integration intensity is obtained, and the He / (He + D) fuel component ratio is calculated on line. A calculation result is read by a plasma control system and then input into a PID controller, the opening degree of a helium and deuterium inflation valve is automatically adjusted, closed-loop control over the boundary helium and deuterium ratio in the discharging process is achieved, and energy constraint deterioration and fusion performance reduction caused by too high He / D are restrained.

The application provides a super-wide-angle free curved surface catadioptric image-side telecentric lens, a design method thereof and an imaging system, and aims at solving the technical problem that the existing super-wide-angle lens is usually a transmission lens and is difficult to observe plasma in an environment with large temperature difference. The super-wide-angle free curved surface catadioptric image-side telecentric lens fully considers the high-temperature environment when observing plasma in a tokamak device, and innovatively adds a reflection light path, so that the lens is divided into three parts, namely, an aperture diaphragm, a reflection light path and a transmission light path. The aperture diaphragm and the reflection light path are made of metal and are arranged in a high-temperature vacuum chamber between a first observation window and a second observation window of the tokamak device. The lenses in the transmission light path are made of traditional lens materials and are arranged in a room-temperature environment outside the lenses, so that the super-wide-angle free curved surface catadioptric image-side telecentric lens can realize stable observation of plasma when the tokamak device works.