Gas injection device, method for a fusion reactor
By combining turbocharging and fast valves, the pressure and response speed issues of gas injection in tokamak devices were resolved, achieving efficient, rapid, and controllable gas injection, which meets the requirements of rapid density control and impurity radiation regulation in fusion reactors.
Patent Information
- Application Number
- CN202511962964.9
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- Filing Date
- 2025-12-24
- Publication Date
- 2026-02-24
- Estimated Expiration
- 2045-12-24
AI Technical Summary
Existing tokamak gas injection methods suffer from limitations such as injection pressure, insufficient penetration depth, slow response speed, and difficulty in real-time adjustment, failing to meet the requirements of fusion reactors for rapid density control, impurity radiation regulation, and ELM mitigation.
By employing a combination of a turbocharger and a fast valve, a high-speed airflow drives the turbine to rotate and compress the gas, forming a high-pressure gas source. This gas is then released in a pulsed manner through a directional nozzle. Real-time control is achieved by combining a monitoring unit and a control unit to improve the injection pressure and response speed.
It significantly improves gas injection pressure and penetration depth, shortens response time, and enables precise control of gas injection. It is suitable for fuel utilization and impurity radiation control in future fusion reactors, and enhances the H-mode maintenance window and off-target stability.
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Figure CN121393950B_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of fusion engineering technology, and in particular to a gas injection device and method for a fusion reactor. Background Technology
[0002] Currently, most tokamak devices use mechanical pressure regulating valves for gas injection. This method is limited by room temperature gas pressure, slow response speed, and weak deep penetration capability, which makes it unable to meet the requirements of future fusion reactors for rapid density control, impurity radiation regulation, ELM (Edge-Localized Mode) mitigation, and tungsten source reduction. Studies such as CFETR (Chinese Fusion Engineering Test Reactor) and EAST (Experimental Advanced Superconducting Tokamak) have pointed out that although Ar / Ne injection can reduce heat load, it has limitations such as "low injection efficiency, insufficient dynamic adjustment, and difficulty in entering the high-density boundary region".
[0003] To improve injection depth, projectile and compact ring beam injection methods have been proposed in related technologies. However, these methods involve complex equipment, poor real-time performance, and cannot replace gas sources. Meanwhile, integrated simulations such as OMFIT (One Modeling Framework for Integrated Tasks) demonstrate that rapidly adjusting impurity injection is crucial for maintaining the H-mode and achieving target miss.
[0004] Therefore, in order to meet the requirements of fusion reactors for efficient, rapid, and controllable gas injection, there is an urgent need for a new gas injection method that can increase injection pressure, shorten response time, and achieve precise control. Summary of the Invention
[0005] The purpose of this invention is to provide a gas injection device and method for fusion reactors to meet the requirements of fusion reactors for efficient, rapid and controllable gas injection, increase injection pressure, shorten response time, and achieve precise control.
[0006] In a first aspect, embodiments of the present invention provide a fusion reactor gas injection device, the device comprising: a drive gas supply unit for providing a high-speed gas flow; a turbocharger unit including a turbine and a compressor impeller coaxially connected, the inlet of the turbine being connected to the drive gas supply unit, and the inlet of the compressor impeller being used to introduce the working gas to be injected, wherein the turbine is driven to rotate by the high-speed gas flow, thereby driving the compressor impeller to rotate to compress the working gas; a high-pressure chamber, the inlet of which is connected to the outlet of the compressor impeller, for storing the compressed working gas to form a high-pressure gas source; a fast valve disposed on the outlet pipe of the high-pressure chamber for pulsed release of the high-pressure gas source; and a directional nozzle connected downstream of the fast valve for injecting the released working gas into the plasma boundary region of the fusion reactor.
[0007] In some embodiments, the drive gas supply unit includes at least one of the following:
[0008] The helium coolant branch of the fusion reactor;
[0009] The suction gas pipeline of the vacuum pumping system for a fusion reactor;
[0010] An auxiliary working gas supply pipeline independent of the fusion reactor.
[0011] In some embodiments, the high-pressure chamber is made of high-temperature resistant metal or ceramic material, and its pressure range is from tens of kilopascals to hundreds of kilopascals, and it is directly connected to the fast valve via a short path.
[0012] In some embodiments, the fast valve is a high-speed solenoid valve or a piezoelectric ceramic valve, with a response time on the order of sub-milliseconds and a modulation frequency range of tens of hertz to kilohertz.
[0013] In some embodiments, the directional nozzle is a conical nozzle, a slit nozzle, or an ultrasonic nozzle, and its nozzle direction is configured to point towards the high gradient region, the X-point region, or the radiation layer region above the divertor target plate in the plasma boundary region.
[0014] In some embodiments, the apparatus further includes: a monitoring unit for monitoring the state parameters of the plasma; and a control unit, communicatively connected to the monitoring unit, the fast valve, the turbocharger unit, and the directional nozzle, for generating control commands based on the state parameters to adjust the duty cycle or pulse frequency of the fast valve, and / or the rotational speed and / or compressed air volume of the turbocharger unit, and / or the nozzle direction and / or injection momentum of the directional nozzle.
[0015] In a second aspect, embodiments of the present invention provide a fusion reactor gas injection method for use in the fusion reactor gas injection device described in the first aspect embodiment. The method includes: obtaining a driving gas source from a driving gas supply unit to form a high-speed airflow; using the high-speed airflow to drive the turbine in the turbocharger unit to rotate, and driving the compressor impeller to rotate, so as to pressurize the working gas introduced from the outside; storing the pressurized working gas in a high-pressure chamber to form a high-pressure gas source; performing pulsed release control on the high-pressure gas source through a fast valve; and injecting the released working gas into the plasma boundary region of the fusion reactor through a directional nozzle.
[0016] In some embodiments, the method further includes: monitoring the state parameters of the plasma; and generating control commands based on the state parameters to adjust the duty cycle or pulse frequency of the fast valve, and / or the rotational speed and / or compressed air volume of the turbocharger unit, and / or the nozzle direction and / or injection momentum of the directional nozzle.
[0017] In some embodiments, the state parameters include at least one of the following: the boundary local mode precursor signal of the plasma, the density change rate, the boundary radiation power, and the spatial distribution characteristics of impurities.
[0018] In some embodiments, generating control commands based on the state parameters to adjust the duty cycle or pulse frequency of the fast valve, and / or the rotational speed and / or compressed air volume of the turbocharger unit, and / or the nozzle direction and / or injection momentum of the directional nozzle includes: generating a first control command based on the density change rate to adjust the duty cycle or pulse frequency of the fast valve to achieve density closed-loop control; and / or generating a second control command based on the boundary radiation power to adjust the rotational speed and / or compressed air volume of the turbocharger unit to achieve radiation closed-loop control; and / or generating a third control command based on the impurity spatial distribution characteristics to adjust the nozzle direction and / or injection momentum of the directional nozzle to achieve impurity distribution closed-loop control; and / or generating a fourth control command based on the boundary local mode precursor signal to trigger, gate, or limit the output of the density closed-loop control, the radiation closed-loop control, and / or the impurity distribution closed-loop control.
[0019] The fusion reactor gas injection device and method of this invention, during gas injection into the fusion reactor, provides a high-speed airflow through a driving gas supply unit, thereby driving the turbine in the turbocharger unit to rotate and in turn driving the compressor impeller to rotate, thus compressing the introduced working gas; the compressed working gas is stored in a high-pressure chamber to form a high-pressure gas source; the high-pressure gas source is pulsedly released through a fast valve, and the released working gas is injected into the plasma boundary region of the fusion reactor through a directional nozzle. Thus, the turbocharger can increase the injection pressure, the fast valve can shorten the response time, and the directional nozzle enables precise control. Attached Figure Description
[0020] Figure 1 This is a schematic diagram of the structure of a fusion reactor gas injection device according to an embodiment of the present invention;
[0021] Figure 2 This is a schematic diagram of the nozzle direction of a directional nozzle according to an embodiment of the present invention;
[0022] Figure 3 This is a schematic diagram of the structure of a fusion reactor gas injection device according to another embodiment of the present invention;
[0023] Figure 4 This is a schematic diagram of the structure of a fusion reactor gas injection device according to a specific embodiment of the present invention;
[0024] Figure 5 This is a flowchart of the operation of a fusion reactor gas injection device according to an embodiment of the present invention;
[0025] Figure 6 This is a flowchart of a fusion reactor gas injection method according to an embodiment of the present invention;
[0026] Figure 7 This is a flowchart of a fusion reactor gas injection method according to another embodiment of the present invention. Detailed Implementation
[0027] The fusion reactor gas injection device and method proposed in this invention aim to solve key problems existing in tokamak gas injection, such as "limited injection pressure, insufficient penetration depth, slow response speed, difficulty in real-time adjustment, and inability to maintain high-flow-rate, high-back-pressure injection." These problems directly affect key operational indicators such as impurity radiation control efficiency, fuel utilization efficiency, H-mode boundary stability, and divertor thermal load control. This is particularly true in next-generation devices such as CFEDR, where the requirements for Ar / Ne radiation distribution control, ELM suppression, and density feedback are even more stringent. The fusion reactor gas injection device proposed in this invention is compact, can be directly integrated near the vacuum chamber, and can achieve gas dynamic pressure and mass flow rate several times higher than traditional methods through "turbocharging," enabling high-performance gas injection with millisecond-level modulation.
[0028] Embodiments of the present invention are described in detail below, examples of which are illustrated in the accompanying drawings, wherein the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and intended to explain the present invention, and should not be construed as limiting the present invention.
[0029] The following description, with reference to the accompanying drawings, describes a fusion reactor gas injection apparatus and method according to embodiments of the present invention.
[0030] Figure 1 This is a schematic diagram of a fusion reactor gas injection device according to an embodiment of the present invention.
[0031] like Figure 1 As shown, the fusion reactor gas injection device 100 includes: a drive gas supply unit 10, a turbocharger unit 20, a high-pressure chamber 30, a fast valve 40, and a directional nozzle 50.
[0032] See Figure 1 The drive gas supply unit 10 provides a high-speed airflow. The turbocharger unit 20 includes a coaxially connected turbine 21 (which can be a micro-turbine, a compact, small-sized, high-speed turbine mechanical structure specifically designed to efficiently convert the kinetic energy of a high-speed airflow into rotational mechanical energy) and a compressor impeller 22. The inlet of the turbine 21 is connected to the drive gas supply unit, and the inlet of the compressor impeller 22 is used to introduce the working gas to be injected. The turbine 21 is driven to rotate by the high-speed airflow, which in turn drives the compressor impeller 22 to rotate, compressing the working gas. The inlet of the high-pressure chamber 30 is connected to the outlet of the compressor impeller 22, storing the compressed working gas to form a high-pressure gas source. A quick valve 40 is located on the outlet pipe of the high-pressure chamber 30 for pulsed release of the high-pressure gas source. A directional nozzle 50 is connected downstream of the quick valve 40 to inject the released working gas into the plasma boundary region of the fusion reactor.
[0033] The turbine 21 can be constructed using a radial impeller or swept blades to achieve impeller speeds of tens of thousands to hundreds of thousands of rpm, thereby increasing the static and dynamic pressures of the working gas to levels that traditional mechanical injection or pulse valves cannot provide, by 2–10 times.
[0034] In this embodiment, the turbocharger unit 20, the fast valve 40, and the directional nozzle 50 can all be electrically controlled, such as controlling the rotational speed of the turbine 21 and the compressed air volume of the compressor impeller 22, the duty cycle or pulse frequency of the fast valve 40, the nozzle direction of the directional nozzle 50, and / or the injection momentum as needed. During gas injection into the fusion reactor, a high-speed airflow is provided by the drive gas supply unit 10, thereby driving the turbine 21 in the turbocharger unit 20 to rotate, which in turn drives the compressor impeller 22 to rotate, compressing the introduced working gas. The compressed working gas is stored in the high-pressure chamber 30, forming a high-pressure gas source. The high-pressure gas source is pulsedly released through the fast valve 40, and the released working gas is injected into the plasma boundary region of the fusion reactor through the directional nozzle 50. Thus, the injection pressure can be increased by turbocharging, the response time can be shortened by the fast valve, and precise control can be achieved through the directional nozzle.
[0035] For example, the driving gas supply unit 10 includes at least one of the following:
[0036] The helium coolant branch of a fusion reactor;
[0037] The suction gas pipeline of the vacuum pumping system for a fusion reactor;
[0038] An auxiliary working gas supply pipeline independent of the fusion reactor.
[0039] To obtain a high-speed gas flow from the helium coolant branch of the fusion reactor, a branch with a regulating valve can be drawn from the main helium coolant circulation pipeline (usually a high-pressure closed loop). The end of this branch connects to the inlet of turbine 21 (which may be equipped with nozzles for gas flow acceleration). After the high-pressure helium is throttled and depressurized by the regulating valve, it expands rapidly at the inlet of turbine 21, converting pressure potential energy into high-speed kinetic energy, forming a high-speed jet that directly impacts the blades of turbine 21, causing them to rotate. This method directly utilizes the energy of the existing, continuously operating high-pressure coolant system of the fusion reactor, requiring no additional power source and exhibiting high system integration. Furthermore, the helium coolant system itself requires stable operation, thus providing a continuous and stable driving gas flow, suitable for scenarios requiring long-term, steady-state gas injection.
[0040] To obtain high-speed gas flow from the "vacuum pumping system of the fusion reactor," a Venturi tube or jet pump ejector can be installed on the main pumping line connecting the divertor vacuum chamber and the high-speed pump (such as a cryogenic pump or vortex pump). The high-speed pumping gas flow (mainly composed of unburned fuel and impurity gases) acts as the "jet flow," passing through the narrow throat of the ejector and creating a localized low-pressure zone. An auxiliary driving gas (such as nitrogen) is introduced into this low-pressure zone, where it is entrained, mixed, and accelerated by the high-speed jet flow, forming a mixed gas flow with enhanced flow rate and velocity, driving the downstream turbine 21. This method cleverly utilizes the exhaust gas that must be continuously discharged during fusion reactor operation as the primary driving force, achieving partial energy recovery. Furthermore, the entire driving gas path is located on the negative pressure side of the vacuum system; even if a leak occurs, it is only external gas leaking inwards, avoiding the risk of high-pressure gas accidentally being injected into the vacuum chamber.
[0041] To obtain a high-speed gas flow from an auxiliary working gas supply line independent of the fusion reactor, a completely independent gas supply system can be established, including high-pressure cylinders (or compressors), pressure reducing valves, precision regulating valves, and flow controllers. The high-pressure cylinders provide initial pressure (typically 10-15 MPa), which, after multi-stage pressure reduction and precision regulation, delivers gas (such as high-purity nitrogen or helium) stabilized at the set pressure and flow rate to the inlet of turbine 21, driving turbine 21 to rotate. This method is completely decoupled from the reactor system, offering the most flexible and fastest response, allowing for rapid and precise adjustment of pressure and flow rate, thus achieving instantaneous, wide-range control of turbine 21 speed and pressurization capacity. Furthermore, the driving gas source can use inert, dry, pure gas, resulting in minimal wear on turbine 21 and high system reliability; it is not dependent on specific reactor types or operating modes, making it suitable for various experimental devices and reactors, demonstrating strong versatility.
[0042] In practical design, one or a combination of schemes (such as using an independent gas source for rapid control and a coolant branch as a steady-state backup) can be selected based on the specific reactor design concept, safety specifications, cost control, and required injection performance (such as response speed and pressure ratio limit) to achieve optimal reliability, economy and performance.
[0043] For example, the high-pressure chamber 30 is made of high-temperature resistant metal or ceramic material, and its pressure range is from tens of kilopascals to hundreds of kilopascals, and it is directly connected to a fast valve via a short path.
[0044] Specifically, the pressurized working gas is temporarily stored in a small high-pressure chamber 30 to eliminate instantaneous pressure unevenness caused by fluctuations in the turbine 21's speed, while also providing a pressure source for subsequent gas pulse injection. The high-pressure chamber 30 can be made of high-temperature resistant metal or ceramic materials, capable of withstanding injection pressures of tens to hundreds of kilopascals, and can form a short-path connection with the quick valve 40 to reduce pipeline damping.
[0045] For example, the fast valve 40 is a high-speed solenoid valve or a piezoelectric ceramic valve with a response time in the sub-millisecond range and a modulation frequency range in the tens of hertz to kilohertz range.
[0046] Specifically, the rapid valve 40 can be a high-speed solenoid valve or a piezoelectric ceramic rapid valve. By modulating the outlet of the high-pressure chamber 30, pulse gas injection requirements ranging from tens of hertz to over kilohertz can be met.
[0047] Optionally, the control of the fast valve 40 can be linked with the plasma real-time diagnostic system. For example, the fast valve 40 can be controlled according to the plasma density change rate, boundary radiation power change, ELM precursor signal, etc., so that the gas injection volume can be automatically adjusted according to the instantaneous plasma state.
[0048] For example, the directional nozzle 50 is a conical nozzle, a slit nozzle, or an ultrasonic nozzle, and its nozzle direction is configured to point towards the high gradient region, the X-point region, or the radiation layer region above the divertor target plate in the plasma boundary region.
[0049] Specifically, after the rapid valve 40, high-pressure gas can be directed towards the plasma boundary region via a directional nozzle 50. The directional nozzle 50 can be designed as a conical, slit-type, or ultrasonic nozzle to obtain a high-speed, highly directional gas jet, thereby reducing diffusion losses in the SOL (Scrape-Off Layer) region and allowing more gas to penetrate the high-density boundary layer into the desired region. The nozzle orientation and position can be optimized according to the geometry of the tokamak device, such as facing the X-point, the radiation layer region above the divertor target, or the high-gradient region near the main plasma boundary, to maximize the efficiency of radiation control or refueling. Figure 2 Three nozzle directions are shown: nozzle direction I facing the X-point region, nozzle direction II pointing towards the high gradient region of the plasma boundary, and nozzle direction III (two in number) pointing towards the divertor radiation layer region. Figure 2 The elliptical line between the intermediate scraping layer and the main plasma represents the interface, and the intersection of the interface is point X.
[0050] In some examples, the nozzle direction and / or injection momentum of the directional nozzle 50 are adjustable, thereby improving injection accuracy and efficiency.
[0051] The adjustable nozzle direction is achieved as follows:
[0052] Method 1: The directional nozzle 50 is fixed on a platform that can rotate around a single axis (pitch) or two axes (pitch + yaw). The platform is driven by a high-precision stepper motor or servo motor, and the angle is adjusted through reduction gears or direct drive. During control, pulse signals can be sent to the motor according to preset coordinates or real-time feedback to precisely control the rotation angle. An angle sensor (such as an encoder) can be embedded to achieve closed-loop position feedback.
[0053] This method has a relatively simple structure and is suitable for scenarios that require a large range of angle adjustments, such as changing the injection point to the target plate area (e.g., switching from the inner target plate to the outer target plate).
[0054] Method 2: Connect the directional nozzle 50 to the end of the downstream air supply line of the quick valve 40 via a universal ball joint. The outer shell of the ball joint is fixed, while the internal ball can swing in multiple directions at small angles (e.g., ±15°). A metal bellows or special flexible seals are used to ensure a vacuum seal. Multiple piezoelectric ceramic actuators or miniature linear motors can be arranged around the ball joint. By coordinating the extension / retraction of each actuator to push and pull the ball, the nozzle direction can be finely adjusted.
[0055] This method has a fast response speed (especially piezoelectric drive), making it suitable for high-frequency, small-amplitude dynamic fine-tuning to compensate for rapid fluctuations in the plasma boundary position or to achieve scanning injection.
[0056] Method 3: Multiple directional nozzles 50 with fixed directions can be pre-positioned in key areas (such as the upper and lower divertors, near the X point), with each directional nozzle 50 pointing to a specific target area (such as the high gradient region, the X point, or the radiation layer). Each directional nozzle 50 is controlled by an independent high-speed valve at its front end, and "electronic" direction switching can be achieved by selecting to open different nozzles or combinations.
[0057] This method has no moving parts, is highly reliable, and the switching speed depends on the valve response speed.
[0058] The injection momentum is related to the square of the gas density and velocity, and its regulation can be achieved by adjusting the upstream gas state. For example, adjusting the turbine speed of the turbocharger unit 20, adjusting the duty cycle of the quick valve 40, and the pulse frequency.
[0059] Figure 3 This is a schematic diagram of the structure of a fusion reactor gas injection device according to another embodiment of the present invention.
[0060] like Figure 3 As shown, compared to Figure 1 The embodiment shown further includes a monitoring unit 60 and a control unit 70 in the fusion reactor gas injection device 100.
[0061] The monitoring unit 60 is used to monitor the state parameters of the plasma; the control unit 70 is communicatively connected to the monitoring unit 60, the rapid valve 40, the turbocharger unit 20, and the directional nozzle 50 (see [link]). Figure 3 The dashed line in the figure is used to generate control commands based on the state parameters to adjust the duty cycle or pulse frequency of the fast valve 40, and / or the speed and / or compressed air volume of the turbocharger unit 20, and / or the nozzle direction and / or injection momentum of the directional nozzle 50.
[0062] The state parameters may include at least one of the following: the boundary local mode precursor signal of the plasma, the density change rate, the boundary radiation power, and the spatial distribution characteristics of impurities.
[0063] In some embodiments, control commands are generated based on state parameters to adjust the duty cycle or pulse frequency of the fast valve, and / or the rotational speed and / or compressed air volume of the turbocharger unit 20, and / or the nozzle direction and / or injection momentum of the directional nozzle 50. This includes: generating a first control command based on the density change rate to adjust the duty cycle or pulse frequency of the fast valve 40 to achieve density closed-loop control; and / or generating a second control command based on the boundary radiation power to adjust the rotational speed and / or compressed air volume of the turbocharger unit 20 to achieve radiation closed-loop control; and / or generating a third control command based on the spatial distribution characteristics of impurities to adjust the nozzle direction and / or injection momentum of the directional nozzle to achieve impurity distribution closed-loop control; and / or generating a fourth control command based on the boundary local mode precursor signal to trigger, gate, or limit the output of the density closed-loop control, radiation closed-loop control, and / or impurity distribution closed-loop control.
[0064] In this embodiment, the fusion reactor gas injection device 100 can be linked with the plasma system. The general principle of the linkage is to map diagnostic quantities to risk indicators, and then to the duty cycle or pulse frequency of the fast valve 40, the rotational speed and / or compressed air volume of the turbocharger unit 20, the nozzle direction of the directional nozzle 50 and / or the injection momentum, etc.
[0065] For example, regarding density, the density measurement value provided by the tokamak diagnostic system can be used to determine whether the rate of density increase is too high or too low. The determination signal is transmitted to the control unit 70, which can control the duty cycle or valve frequency of the fast valve 40. If the density increases too quickly, the gas injection will be reduced in advance to prevent overshoot; conversely, if the density decreases too quickly, the gas injection will be increased in advance.
[0066] Regarding radiation power, the thermal radiation measurement of the diagnostic system or the radiation signal of the divertor can be used to determine whether the radiation is close to the HL conversion threshold and safety constraint value. The signal is transmitted to the control unit 70. If the radiation power is lower than the target, the control unit 70 controls the increase of Ar / Ne injection; if the radiation power rises too fast or exceeds the upper limit, the control unit 70 immediately reduces or cuts off the gas injection.
[0067] For impurities, their spectral lines or spatial distribution characteristics in the plasma can be monitored. The nozzle direction of the directional nozzle 50 can be adjusted, and the compressed gas flow rate can be adjusted as needed. When a trend of impurity accumulation towards the main plasma core is detected, the nozzle direction is adjusted to inject more gas into the boundary region or divertor region, reducing impurity penetration into the core. When it is necessary to enhance radiation in a specific region (such as above the divertor), the nozzle direction is adjusted to point towards the corresponding region, and the compressed gas flow rate can be decreased or increased to control the penetration depth of the impurity jet.
[0068] ELM precursor signals are characterized by their suddenness, nonlinearity, and short time windows, making continuous proportional control unsuitable. Instead, event-triggered control strategies based on threshold or pattern recognition are more appropriate. Common ELM precursor signals include the rising slope of the Dα spectral line, changes in the boundary electron density temperature gradient, magnetic disturbances, and anomalous radiation increases; these are combined into an "ELM risk index." When the risk index approaches the threshold, a precursor state is entered. Once an ELM precursor state is detected, the control unit 70 ceases continuous adjustment according to the conventional density or radiation closed-loop control. Instead, it triggers preset actions such as pulsed gas injection, limited gas injection, or gas injection mode switching to actively adjust boundary plasma conditions or suppress instability development. This trigger-based control has higher priority and can gate or override conventional density or radiation closed-loop control to improve the safety and stability of system operation.
[0069] Control commands can be determined by multiple indicators, specifically using a "multi-closed-loop + priority" structure, as follows:
[0070] Density control closed loop: Adjust the duty cycle of the fast valve or the pulse frequency based on density or density change rate;
[0071] Radiation control closed loop: Adjust turbine speed and / or compressor volume based on boundary radiation power;
[0072] Impurity distribution closed loop: Based on the spatial distribution of impurities, adjust the nozzle direction and / or the injection momentum;
[0073] ELM Event Control Loop: Based on ELM precursor signals, it triggers, gates, or limits the above closed loop and has a higher priority.
[0074] The aforementioned closed loops can operate simultaneously. The density control closed loop, radiation control closed loop, and impurity distribution closed loop can run in parallel. The ELM event control loop, which is related to plasma stability and safety, has a higher priority and can cover or limit the output of other closed loops when necessary, triggering, gating, or limiting the gas injection to ensure stability and safety.
[0075] The following is combined with Figure 4 , Figure 5 The fusion reactor gas injection device 100 and its working principle are described in an embodiment of the present invention.
[0076] like Figure 4 As shown, the fusion reactor gas injection device 100 includes a drive gas supply unit 10, a turbocharger unit 20, a high-pressure chamber 30, a fast valve 40, directional nozzles 50, a monitoring unit 60, and a control unit 70. In the upper gas supply and pressure stabilization module, the compressor blades 22 in the turbocharger unit 20 act as a pressure boosting module, introducing working gas (i.e., the gas to be injected, such as fuel gas or impurity gas) from an external gas supply module. After compressing the working gas, it is transmitted to the high-pressure chamber 30 for energy storage and pressure stabilization, thus obtaining a high-pressure gas source. In the main gas injection link (execution section), the high-pressure gas source can be released to the directional nozzles 50 (the number of which is n, and they can be axially set, tilted, or set as nozzles, etc.) through the fast valves 40 (such as solenoid valves or piezoelectric valves). The gas is then sprayed into the plasma boundary region through the directional nozzles 50, including the X-point region, the radiation layer region above the target plate, and the high gradient region of the plasma boundary. Subsequently, the state parameters of the plasma can be monitored by the monitoring unit 60, and the control unit can control the fast valve 40 and / or the turbine 21 according to the state parameters. The turbine 21 can be driven to rotate by a high-speed airflow provided by the driving air supply unit, so as to drive the compressor blades 22 to rotate and thus pressurize the working gas.
[0077] like Figure 5 As shown, the overall operation of the fusion reactor gas injection device 100 includes: acquisition of driving gas source, turbine drive, compressor impeller pressurization, high-pressure chamber temporary storage, fast valve modulation injection, directional nozzle injection, and linkage with real-time closed-loop control of plasma. Specifically, driving energy can first be obtained from three types of optional driving gas sources: first, a steady-state high-speed helium flow from the helium coolant branch; second, a continuous suction gas flow generated by the tokamak vacuum pumping system; and third, the flow driving force formed by independent auxiliary working gases (such as helium / nitrogen). These flows can provide input kinetic energy to the micro turbine without the need for additional large equipment. After the driving gas source enters the turbine 21, it drives the compressor impeller 22, which is coupled to it via a shaft, to rotate at high speed, giving the working gas to be injected a secondary mechanical boost.
[0078] The pressurized working gas is temporarily stored in a small high-pressure chamber 30 to eliminate instantaneous pressure inhomogeneities caused by turbine speed fluctuations, while also providing a pressure source for subsequent pulse injection. Subsequently, a fast valve 40 modulates the outlet of the high-pressure chamber 30 to meet pulse injection requirements ranging from tens of hertz to over kilohertz. The control signal of the fast valve 40 can be linked with a real-time plasma diagnostic system, monitoring parameters such as density change rate, boundary radiation power changes, and ELM precursors, enabling automatic adjustment of the injection volume based on the instantaneous plasma state. Following the fast valve 40, the high-pressure gas is directed towards the plasma boundary through a directional nozzle 50.
[0079] The fusion reactor gas injection device 100 can form a closed-loop feedback with the plasma control system. By monitoring density, radiation, impurity distribution, and ELM activity in real time, it can automatically adjust turbine speed, compressed gas volume, pulse valve duty cycle, and injection direction to meet complex operational requirements such as target stabilization, boundary radiation homogenization, and H-mode maintenance. This method not only significantly improves injection dynamic pressure and depth but also enhances response speed and adjustment flexibility, making it suitable for fuel injection and impurity radiation control in future fusion reactors such as CFEDR and ITER.
[0080] It should be noted that, in addition to the turbocharging achieved by driving the turbine 21 with high-speed airflow provided by the driving air supply unit 10, other methods can also be used to drive the turbine 21, such as using a dedicated micro motor. Compared to high-speed airflow drive, motor drive can achieve more independent boost control. The specific shape and driving method of the turbine 21 and compressor impeller 22, as well as the style of the directional nozzle 50, can all be set as needed to achieve goals such as high-pressure enhancement, rapid modulation, and deep injection.
[0081] The fusion reactor gas injection device 100 of this invention introduces the mechanical supercharging principle of "turbocharging" into the tokamak gas injection system, enabling the injection pressure to break through the physical limits of traditional bottled gas and pressure reducing valves, achieving a dynamic pressure enhancement of 2-10 times or more. Through a high-speed rotating impeller and a micro-pressurization chamber, the injected gas possesses significantly enhanced penetration capability, thus achieving deep injection even in high-density boundary plasma environments, improving fuel utilization efficiency and impurity radiation control accuracy. It can respond to plasma state changes at millisecond or even sub-millisecond levels, achieving injection modulation performance far faster than existing mechanical valves and pulse valves, making it suitable for advanced control tasks such as ELM suppression, radiation control, and W contamination suppression. The fusion reactor gas injection device 100 has a compact structure and can be arranged close to the vacuum chamber, reducing pipeline damping and greatly improving injection dynamic performance. Furthermore, this invention possesses "closed-loop automatic control" capability, capable of adjusting the injection waveform in real time based on plasma diagnostic signals such as density, radiation, and ELM precursors.
[0082] Figure 6 This is a flowchart of a fusion reactor gas injection method according to an embodiment of the present invention.
[0083] In this embodiment, the fusion reactor gas injection method is used in the fusion reactor gas injection device described in the above embodiment.
[0084] like Figure 6 As shown, the gas injection method for fusion reactors includes:
[0085] S11 obtains driving air from the driving air supply unit to form a high-speed airflow.
[0086] S12 uses high-speed airflow to drive the turbine in the turbocharger unit to rotate, which in turn drives the compressor impeller to rotate, thereby pressurizing the working gas introduced from the outside.
[0087] S13 stores the pressurized working gas in the high-pressure chamber to form a high-pressure gas source.
[0088] S14 controls the pulse release of the high-pressure gas source through a fast valve.
[0089] S15 injects the released working gas into the plasma boundary region of the fusion reactor through a directional nozzle.
[0090] In some embodiments of the present invention, such as Figure 7 As shown, the fusion reactor gas injection method also includes:
[0091] S21, monitors the state parameters of the plasma.
[0092] S22 generates control commands based on state parameters to adjust the duty cycle or pulse frequency of the fast valve, and / or the speed and / or compressed air volume of the turbocharger unit, and / or the nozzle direction and / or injection momentum of the directional nozzle.
[0093] The state parameters may include at least one of the following: the boundary local mode precursor signal of the plasma, the density change rate, the boundary radiation power, and the spatial distribution characteristics of impurities.
[0094] In some implementations, control commands are generated based on state parameters to adjust the duty cycle or pulse frequency of the fast valve, and / or the rotational speed and / or compressed air volume of the turbocharger, and / or the nozzle direction and / or injection momentum of the directional nozzle. This includes: generating a first control command based on the density change rate to adjust the duty cycle or pulse frequency of the fast valve to achieve density closed-loop control; and / or generating a second control command based on the boundary radiation power to adjust the rotational speed and / or compressed air volume of the turbocharger to achieve radiation closed-loop control; and / or generating a third control command based on the spatial distribution characteristics of impurities to adjust the nozzle direction and / or injection momentum of the directional nozzle to achieve impurity distribution closed-loop control; and / or generating a fourth control command based on the boundary local mode precursor signal to trigger, gate, or limit the output of the density closed-loop control, radiation closed-loop control, and / or impurity distribution closed-loop control.
[0095] It should be noted that for other specific embodiments of the fusion reactor gas injection method of the present invention, please refer to the specific embodiments of the fusion reactor gas injection device of the above embodiments.
[0096] In summary, the fusion reactor gas injection device and method of this invention, by adopting a turbocharger configuration, can significantly increase the gas injection pressure and kinetic energy, enabling the gas to penetrate the boundary high-density layer and improve the effective utilization rate of entering the plasma, thereby reducing losses caused by the rapid removal of impurities or fuel in the SOL. Its millisecond or even sub-millisecond rapid adjustment capability allows it to be linked in real time with phenomena such as ELM precursors, radiation inhomogeneity, and W radiation enhancement, achieving advanced control. At the same time, due to the compact structure of the device, it can be arranged close to the vacuum chamber, thereby reducing pipeline losses and improving response speed. Compared with existing gas injection methods, this invention can significantly improve the radiation homogenization capability of Ar / Ne injection in CFEDR, increase the H-mode maintenance window, enhance off-target stability, improve fuel efficiency, and reduce the energy consumption and complexity of the gas injection system, thus having significant engineering and application value.
[0097] It should be understood that various parts of the present invention can be implemented in hardware, software, firmware, or a combination thereof. In the above embodiments, multiple steps or methods can be implemented in software or firmware stored in memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, it can be implemented using any one or a combination of the following techniques known in the art: discrete logic circuits having logic gates for implementing logical functions on data signals, application-specific integrated circuits (ASICs) having suitable combinational logic gates, programmable gate arrays (PGAs), field-programmable gate arrays (FPGAs), etc.
[0098] In the description of this specification, references to terms such as "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., indicate that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of the invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples.
[0099] In the description of this invention, it should be understood that the terms "center," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," and "circumferential" indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are used only for the convenience of describing this invention and simplifying the description, and are not intended to indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on this invention.
[0100] Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of that feature. In the description of this invention, "a plurality of" means at least two, such as two, three, etc., unless otherwise explicitly specified.
[0101] In this invention, unless otherwise explicitly specified and limited, the terms "installation," "connection," "linking," and "fixing," etc., should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components, unless otherwise explicitly limited. Those skilled in the art can understand the specific meaning of the above terms in this invention according to the specific circumstances.
[0102] In this invention, unless otherwise explicitly specified and limited, "above" or "below" the second feature can mean that the first feature is in direct contact with the second feature, or that the first feature is in indirect contact with the second feature through an intermediate medium. Furthermore, "above," "over," and "on top" of the second feature can mean that the first feature is directly above or diagonally above the second feature, or simply that the first feature is at a higher horizontal level than the second feature. "Below," "below," and "under" the second feature can mean that the first feature is directly below or diagonally below the second feature, or simply that the first feature is at a lower horizontal level than the second feature.
[0103] Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention. Those skilled in the art can make changes, modifications, substitutions and variations to the above embodiments within the scope of the present invention.
Claims
1. A fusion reactor gas injection device, characterized in that, The device includes: Drive air supply unit, used to provide high-speed airflow; The turbocharger unit includes a turbine and a compressor impeller coaxially connected. The inlet of the turbine is connected to the drive air supply unit, and the inlet of the compressor impeller is used to introduce the working gas to be injected. The turbine is driven to rotate by the high-speed airflow, which in turn drives the compressor impeller to rotate, thereby compressing the working gas. The high-pressure chamber, whose inlet is connected to the outlet of the compressor impeller, is used to store the compressed working gas and form a high-pressure gas source; A quick-release valve is installed on the outlet pipe of the high-pressure chamber for pulsed release of the high-pressure gas source; A directional nozzle, connected downstream of the fast valve, is used to inject the released working gas into the plasma boundary region of the fusion reactor. A monitoring unit is used to monitor the state parameters of the plasma; The control unit is communicatively connected to the monitoring unit, the fast valve, the turbocharger unit, and the directional nozzle, respectively, and is used to generate control commands based on the status parameters to adjust the duty cycle or pulse frequency of the fast valve, and / or the rotational speed and / or compressed air volume of the turbocharger unit, and / or the nozzle direction and / or injection momentum of the directional nozzle.
2. The fusion reactor gas injection device according to claim 1, characterized in that, The drive gas supply unit includes at least one of the following: The helium coolant branch of the fusion reactor; The suction gas pipeline of the vacuum pumping system for a fusion reactor; An auxiliary working gas supply pipeline independent of the fusion reactor.
3. The fusion reactor gas injection device according to claim 1, characterized in that, The high-pressure chamber is made of high-temperature resistant metal or ceramic material, and its pressure range is from tens of kilopascals to hundreds of kilopascals. It is directly connected to the fast valve via a short path.
4. The fusion reactor gas injection device according to claim 1, characterized in that, The fast valve is a high-speed solenoid valve or a piezoelectric ceramic valve, with a response time in the sub-millisecond range and a modulation frequency range in the tens of hertz to kilohertz range.
5. The fusion reactor gas injection device according to claim 1, characterized in that, The directional nozzle is a conical nozzle, a slit nozzle, or an ultrasonic nozzle, and its nozzle direction is configured to point towards the high gradient region, the X-point region, or the radiation layer region above the divertor target plate in the plasma boundary region.
6. A method for injecting gas into a fusion reactor, characterized in that, For a fusion reactor gas injection device as described in any one of claims 1-5, the method comprises: Driven air is obtained from the drive air supply unit to form a high-speed airflow; The high-speed airflow drives the turbine in the turbocharger unit to rotate, which in turn drives the compressor impeller to rotate, thereby pressurizing the working gas introduced from the outside. The pressurized working gas is stored in the high-pressure chamber to form a high-pressure gas source; The high-pressure gas source is controlled by a pulse release via a fast valve; The released working gas is injected into the plasma boundary region of the fusion reactor through a directional nozzle; The method further includes: Monitor the state parameters of the plasma; Based on the state parameters, control commands are generated to adjust the duty cycle or pulse frequency of the fast valve, and / or the rotational speed and / or compressed air volume of the turbocharger unit, and / or the nozzle direction and / or injection momentum of the directional nozzle.
7. The fusion reactor gas injection method according to claim 6, characterized in that, The state parameters include at least one of the following: the boundary local mode precursor signal of the plasma, the density change rate, the boundary radiation power, and the spatial distribution characteristics of impurities.
8. The fusion reactor gas injection method according to claim 7, characterized in that, The step of generating control commands based on the state parameters to adjust the duty cycle or pulse frequency of the fast valve, and / or the rotational speed and / or compressed air volume of the turbocharger unit, and / or the nozzle direction and / or injection momentum of the directional nozzle, includes: Based on the density change rate, a first control command is generated to adjust the duty cycle or pulse frequency of the fast valve, thereby achieving closed-loop density control; and / or Based on the boundary radiation power, a second control command is generated to adjust the speed and / or compressor volume of the turbocharger unit, achieving radiation closed-loop control; and / or Based on the spatial distribution characteristics of the impurities, a third control command is generated to adjust the nozzle direction and / or injection momentum of the directional nozzle, thereby achieving closed-loop control of the impurity distribution; and / or Based on the boundary local mode precursor signal, a fourth control command is generated to trigger, gate, or limit the output of the density closed-loop control, the radiation closed-loop control, and / or the impurity distribution closed-loop control.
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