28 results about "Nuclear fusion" patented technology

The application discloses a radiation calorimeter probe of a future fusion reactor and relates to the technical field of magnetic confinement nuclear fusion device diagnosis technology. The probe comprises an external protective sleeve, a chip structure arranged in the internal of the external protective sleeve, an internal fixing structure for fixing the chip structure and a cooling pipeline. The external protective sleeve is made of non-magnetic stainless steel, and the cooling pipeline is arranged in the wall of the external protective sleeve or in the internal space. The chip structure comprises an absorbing film, an insulating layer and a measuring circuit comprising a thermistor which are arranged in sequence. The application realizes stable measurement of radiation power under the extreme environment of the fusion reactor through material optimization and structure integration, improves the reliability and maintenance convenience of the probe and meets the long pulse operation requirement of the future fusion reactor.

This invention relates to the field of nuclear fusion reactor materials technology, specifically to a low-activation ferritic / martensitic steel CLF-1 for nuclear fusion reactor blankets, its preparation method, and its applications. The steel's chemical composition, by mass percentage, is: Cr: 8.0-9.0%, W: 1.4-1.6%, V: 0.2-0.3%, Ta: 0.06-0.1%, Mn: 0.3-0.5%, C: 0.07-0.12%, Gd: 0.03-0.06%, N≤0.02%, with the balance being Fe and unavoidable impurities of a specific content. The microstructure is tempered lath martensite, possessing excellent room-temperature and high-temperature mechanical properties, thermal properties, and radiation resistance. This steel is effectively adapted to the extreme working environment of nuclear fusion reactor blankets and is suitable for manufacturing structural components for nuclear fusion reactor blankets.

The application discloses a sustained combustion type plasma nuclear fusion chamber. The chamber comprises a shell, a plasma channel is arranged in the shell, the plasma channel is a tapered pipeline from an inlet end to an outlet end, the inlet of the plasma channel is communicated with the outlet of an electromagnetic acceleration channel of a plasma electromagnetic acceleration device, the inner end of the plasma channel is communicated with a plasma nuclear fusion cavity, the inner wall of the plasma nuclear fusion cavity is an arc surface, a nuclear fusion sustained combustion cavity is arranged on the inner wall of the plasma nuclear fusion cavity, and the nuclear fusion sustained combustion cavity is filled with nuclear fusion fuel. The sustained combustion type plasma nuclear fusion chamber can make plasma enter the plasma nuclear fusion chamber and generate primary nuclear fusion, and the primary nuclear fusion can transmit heat to the nuclear fusion fuel in the nuclear fusion sustained combustion cavity, thereby triggering secondary nuclear fusion.

The application discloses a method and device for preparing elements on demand by means of controllable nuclear fusion-nuclear transmutation with deuterium (hydrogen isotope) as the only raw material, belonging to the technical field of controllable nuclear physics and element synthesis, and suitable for laboratory small-batch research scenarios. The core is that under controllable conditions in the laboratory, 10-15 MeV high-energy neutrons are generated by deuterium nuclear fusion, and low-radioactivity / stable target materials are directionally bombarded, and stable products such as noble metals and rare earth elements are directionally prepared through nuclear transmutation and decay (1-50g per single preparation), the reaction by-products can be recycled, the fusion energy recovery rate is greater than or equal to 30%, and the external power supply accounts for less than or equal to 70%, which does not constitute unlimited energy output. The total floor area of the device is less than or equal to 10 m2, and the total power is less than or equal to 200 kW, and the device has the advantages of wide raw material sources, environmental friendliness, strong controllability and the like, and can be applied to the fields of noble metal preparation, new energy material synthesis, harmless treatment simulation of nuclear waste and the like, and fills the technical gap of global laboratory-level deuterium-based element preparation on demand.

The present application relates to the technical fields of nuclear fusion research and neutron source, and particularly relates to a poloidal magnetic field plasma focus device, which comprises a vacuum tube, a coaxial electrode assembly and a poloidal magnetic field generating assembly, the coaxial electrode assembly and the poloidal magnetic field generating assembly are arranged in the vacuum tube; the poloidal magnetic field generating assembly comprises a plurality of bar magnets, each of the bar magnets is distributed in a circumferential array around an axis of the vacuum tube, and each of the bar magnets is arranged at an outer periphery of the coaxial electrode assembly, the magnetization directions of adjacent bar magnets are opposite, so that the N poles of the bar magnets and the S poles of the bar magnets are arranged alternately along the circumference, thereby forming a poloidal magnetic field in a discharge region of the coaxial electrode assembly, and the technical problem of low energy utilization efficiency caused by large parasitic inductance of a discharge loop of a traditional plasma focus device is solved.

This invention discloses a method and system for transient analysis of helium leakage in a nuclear fusion device, relating to the field of nuclear fusion safety analysis technology. The method includes the following steps: obtaining the structural parameters and operating parameters of the Dewar radiator of the nuclear fusion device; dividing the internal space of the Dewar radiator into multiple interconnected control volumes based on the structural parameters; establishing a set of transient analysis equations containing target physical quantities for each control volume based on the operating parameters; solving the transient analysis equations using a variable step-size integration method to obtain the transient time histories of the target physical quantities in each control volume; and converting the transient time histories of the target physical quantities into load data files recognizable by the target engineering analysis platform. This method, by dividing the internal space of the Dewar radiator into control volumes and solving the helium leakage transient process based on the divided structures, can accurately predict the pressure and temperature evolution under leakage accidents and generate load files that can be directly used for structural safety assessment, thus improving the efficiency of safety analysis and design optimization capabilities.

This invention relates to the fields of aerospace propulsion and laser communication technology, specifically to an interplanetary laser communication silicon-tritium sphere nuclear fusion laser emission thruster, comprising a silicon-tritium sphere nuclear fusion laser emitter and a laser communication device. By employing nuclear fusion technology, silicon and tritium elements are fused under high temperature and high pressure to generate energy, which is then converted into laser light and emitted, providing powerful propulsion for rockets. This solves the technical problem that existing aerospace propulsion technologies mostly use chemical rockets or ion thrusters, which have low propulsion force and long acceleration times, failing to meet the needs of future deep space exploration. By modulating and demodulating the generated laser signal, rapid data transmission can be achieved, thus solving the technical problem that existing laser communication technologies mostly use semiconductor lasers as the emission source, where the transmission distance and data rate are limited.

The application discloses a kind of nuclear fusion star simulator magnet coil curvature deformation precision scanning measurement device and method, belong to nuclear fusion device precision measurement technical field.Device includes pedestal, support column, outer ring frame, rotary motor sliding seat, radial adjusting rod, main measurement scanning ring probe, center shaft and auxiliary measurement arm;The star simulator magnet coil to be measured is installed in the inside of outer ring frame, rotary motor sliding seat is slid along the circumference of outer ring frame 360 °, radial adjusting rod drives measurement probe to realize radial precision feed, and the supplementary measurement of complex area of coil is completed.Method is realized by establishing unified measurement coordinate system, and three-dimensional point cloud data are collected by full circumferential continuous scanning, and curvature deformation deviation report is generated by curve reconstruction, curvature calculation and comparison with theoretical model.The application solves the problems of low efficiency, insufficient accuracy and inability to continuously scan in full circumferential direction of traditional measurement methods, and the measurement accuracy reaches sub-micron level, providing data support for coil manufacturing, assembly and operation and maintenance.

This application provides a coating system and method for the inner wall surface of a nuclear fusion reactor, and a boronizing reaction system for a fusion device. The coating system includes an inlet assembly, a solid heating assembly, a solid container, and a discharge electrode. The solid container contains solid boron trioxide, and the discharge electrode is located on the inner wall of the reaction chamber of the nuclear fusion reactor. The solid heating assembly is used to heat the solid container. The inlet assembly is used to introduce hydrogen gas into the reaction chamber. The discharge electrode is used to generate positive ions containing boron compounds through glow discharge in the reaction chamber. The positive ions are accelerated in the sheath electric field at the interface between the plasma and the chamber wall, bombarding the inner wall of the reaction chamber to deposit and form a boron film. Boron trioxide, which is low-risk, low-toxicity, and low-cost, is used as a raw material to complete the boronizing coating, enabling the long-term, efficient, low-cost, and safe operation of the nuclear fusion reactor.

The application relates to the field of nuclear fusion devices, and discloses an escape electron mitigation device of a nuclear fusion device, a mitigation method and the nuclear fusion device. The mitigation device comprises an escape electron diagnosis unit for detecting the existence of escape electrons in real time and monitoring the real-time kinetic energy distribution spectrum of an escape electron beam at a high frequency; an adaptive control unit for calculating a resonance frequency capable of causing strong scattering of an electron beam under a current energy state in real time according to the received real-time kinetic energy distribution spectrum of the escape electron beam and in combination with the background magnetic field and density of plasma; and a radio frequency wave injection unit electrically connected or communicatively connected with the adaptive control unit, the radio frequency wave injection unit being capable of dynamically selecting one of radio frequency waves of multiple frequency bands according to the resonance frequency calculated by the adaptive control unit and injecting the radio frequency wave into the plasma. The application can track the energy of escape electrons in real time, and adaptively switch the emission frequency band to rapidly and nonlinearly scatter and dissipate the escape electrons, thereby improving the dissipation efficiency.

This invention discloses a special tooling for processing sectors of a fusion reactor vacuum chamber, belonging to the field of tooling for processing nuclear fusion devices. The tooling includes a trapezoidal central frame, around which a left support, upper support, right support, and lower support are respectively installed. These four supports collectively support the hyperboloid structure components of a large magnetic confinement fusion vacuum chamber. This invention involves suspending the central frame and flipping the tooling, allowing the central frame to provide support for the entire device. The left, upper, right, and lower supports collectively support the hyperboloid structure components of the large magnetic confinement fusion vacuum chamber. The left, upper, right, and lower supports can be disassembled from the central frame, facilitating the sequential clamping and welding of workpieces. This effectively improves the assembly accuracy of different curved surfaces of the vacuum chamber, the processing and manufacturing accuracy of curved structures, reduces costs, and decreases workload.

The application discloses a method, device, medium and equipment for simulating nuclear fusion based on a quantum circuit, and belongs to the field of quantum computing. The method comprises the following steps: constructing a plurality of energy models according to the energy types generated by nuclear fusion reactions; constructing a Hamiltonian H according to the plurality of energy models; calculating eigenvalues of the Hamiltonian H by using a quantum circuit under physical conditions set by the plurality of energy models; obtaining constraint conditions corresponding to electromagnetic energy terms, constraint conditions corresponding to the electromagnetic energy terms and physical conditions corresponding to kinetic energy terms under the eigenvalues of the Hamiltonian H; and inputting the constraint conditions corresponding to the electromagnetic energy terms, the physical conditions corresponding to the kinetic energy terms and the physical conditions corresponding to the kinetic energy terms into a collision model to simulate the nuclear fusion reactions, thereby improving the simulation accuracy and efficiency.

This invention discloses a millimeter-wave power monitoring and compensation method and system for ECRH systems, belonging to the field of magnetic confinement nuclear fusion plasma heating and microwave measurement technology. The invention constructs an offline training dataset with time delay alignment under energy integral constraints to train a millimeter-wave power thermal drift compensation model with detector voltage and detector temperature as inputs. After quantizing the model into a low-bit model, it is deployed on an edge control platform, forming a dual-rate compensation architecture of "slow-loop inference - fast-loop execution": the slow loop periodically infers dynamic compensation coefficients, and the fast loop uses these coefficients to perform real-time linear compensation of the high-speed detector voltage and execute microsecond-level interlocking protection. This invention combines the high-speed response of diode detectors with the high precision of calorimetry, enabling high-precision, low-delay, and highly robust power monitoring and interlocking protection under long-pulse, high-power conditions, significantly improving the safety of fusion device operation and the accuracy of physical analysis.

The invention relates to the field of nuclear fusion devices, and discloses an escape electron relieving device and relieving method of a nuclear fusion device and the nuclear fusion device.The relieving device comprises an escape electron diagnosis unit used for detecting existence of escape electrons in real time and conducting high-frequency monitoring to obtain a real-time kinetic energy distribution spectrum of escape electron beams; the self-adaptive control unit is used for calculating the resonance frequency capable of triggering strong scattering of the electron beam in the current energy state in real time according to the received real-time kinetic energy distribution spectrum of the escape electron beam in combination with the background magnetic field and density of the plasma; and the radio frequency wave injection unit is in electric connection or communication connection with the self-adaptive control unit, and the radio frequency wave injection unit can dynamically select one of radio frequency waves of a plurality of frequency bands according to the resonant frequency calculated by the self-adaptive control unit and inject the radio frequency waves into the plasma. According to the invention, the energy of the escape electrons can be tracked in real time, and the emission frequency band is adaptively switched to realize rapid and nonlinear scattering dissipation of the escape electrons, so that the dissipation efficiency is improved.

The application provides an integrated multi-dimensional magnetic field compensation device, and relates to the technical field of controlled nuclear fusion devices. In the device, planar coils are laid in the circumferential grooves of a sealing flange to generate a parallel magnetic field parallel to the axial direction of an extension structure. The parallel magnetic field is subjected to magnetic field correction and compensation in the z direction. A sleeve structure and a positioning structure are both sleeved in the annular space outside the extension structure and tightly combined with the outer surface of the extension structure and the inner surface of the shell. The outer surface of the sleeve structure comprises a plurality of symmetrically arranged concave spaces, each of which is used for placing a group of coils. The oppositely arranged coil groups generate a same-direction magnetic field. The mutually perpendicularly arranged coil groups generate a vertical magnetic field, which is subjected to magnetic field correction and compensation in the x and y directions. The device is installed outside the vacuum chamber port of a magnetic confinement fusion device, a plurality of magnetic field compensation coils are integrated on the outer surface of the port, and independent regulation and fine compensation of the local three-dimensional magnetic field components of the port region can be realized.

This invention relates to the field of vacuum chamber lifetime assessment technology for nuclear fusion reactors, and in particular to a method for assessing the lifetime of a nuclear fusion reactor vacuum chamber based on a plastic strain correction formula. The proposed method for assessing the lifetime of a nuclear fusion reactor vacuum chamber based on a plastic strain correction formula first constructs a simple finite element analysis model and a plastic strain correction formula; then, it obtains the operating load of the vacuum chamber and infers the stress based on the simple finite element analysis model; finally, it calculates the elastoplastic strain value S of the vacuum chamber under this operating condition using the plastic strain correction formula. total Find the S-N strain fatigue parameter curve of the vacuum chamber structural material and obtain the strain value S. total The corresponding number of fatigue cycles. This invention overcomes the problem that finite element fatigue analysis tools are insufficient for the analysis of vacuum chambers in nuclear fusion reactors, reducing evaluation costs while ensuring evaluation efficiency.

This invention discloses a miniaturized experimental loop for liquid lithium-lead hydrogen isotope injection and extraction, belonging to the field of nuclear fusion reactor blanket experimental technology. It comprises two main modules: a liquid lithium-lead loop and a gas path. The liquid lithium-lead loop uses a sealed pipeline connected in series with a lithium-lead storage tank; the gas path includes hydrogen and argon cylinders, a vacuum pump, and a pressure reducing valve to achieve quantitative hydrogen isotope injection and loop purging pressurization. The experimental section can be equipped with extraction components based on three mainstream technical routes: vacuum permeation window, gas-liquid contactor, and vacuum sieve plate. Two hydrogen isotope sensors monitor the hydrogen concentration in the liquid lithium-lead and can calculate the extraction rate based on the difference. A flow meter is adapted to optimize the flow rate process, and the entire loop is equipped with heating and liquid level monitoring to effectively prevent lithium-lead solidification. This invention features a compact structure, stable operation, and strong adaptability, providing a reliable experimental platform for the verification and parameter optimization of advanced blanket tritium extraction technology in fusion reactors.

The application discloses a firecracker type cyclotron collision beam nuclear fusion power generation device and a power generation method. + The nuclear fusion power generation device adopts double-beam central collision dissociation, D2 The dissociation rate is much higher than that of a traditional single beam dissociation mode, and the deuterium nuclear capture amount and the fusion probability are greatly improved; double-path energy extraction and firecracker type multi-heap relay scheme design solve the unstable problem of fusion energy output and meet the continuous power supply demand; the compact cyclotron and the modularized vacuum cavity design are adopted, so that the device volume is smaller than that of a traditional magnetic confinement fusion device, and the beam parameters obtained by the cyclotron are superior to those of a linear acceleration beam of a traditional Migma device; the method is high in safety, the ions in the device are highly ordered, the fusion neutron flux is low and is completely absorbed, and there is no risk of radioactive leakage, and there is no long-term radioactive waste after the device is decommissioned.

This invention discloses a fusion plasma combustion-assisted method for fusion-fission coupling, belonging to the field of nuclear fusion technology. The method includes: evaluating the parameters of ultrafine fission particles to determine the type of fission material, the total injection volume, particle size, and injection velocity; preparing ultrafine fission particles of the appropriate size based on the evaluation results; and injecting the prepared ultrafine fission particles into the fusion plasma at the determined injection velocity, causing the fission material to undergo a fission reaction in the fusion neutron environment, and using the kinetic energy of the resulting fission fragments to heat the fusion plasma. This invention utilizes the energy release at the megaelectron volt level of the fission reaction for heating, which is an improvement over existing kiloelectron volt level technologies, effectively reducing the fusion ignition conditions and accelerating the fusion research process.

The application discloses a high-energy outgoing electron protection device for a neutral beam injection negative ion source, belongs to the field of the neutral beam injection negative ion source of magnetic confinement nuclear fusion, and mainly comprises a protection plate, a supporting base, a thermocouple and an infrared thermal imager. The protection plate is used for intercepting high-energy outgoing electrons. The supporting base is used for mounting and positioning the protection plate in a beam line vacuum chamber. The thermocouple is used for realizing real-time monitoring of the local temperature of the protection plate. The infrared thermal imager is used for observing a large-area heat source of the protection plate and determining the heat deposition position distribution of the high-energy outgoing electrons. The application realizes protection of heat load sensitive components such as a cryogenic pump by intercepting the high-energy outgoing electron beam and monitoring the deposition position of the high-energy outgoing electron beam, promotes the performance improvement and scheme perfection of an electron suppression means, is favorable for long-pulse stable operation of the negative ion source, and can effectively protect the high-energy outgoing electron in the neutral beam injection negative ion source.

Systems, methods and apparatus are provided through which in some implementations an experimental fusion system includes a housing having a hollow toroidal interior chamber, wherein the hollow toroidal interior chamber includes an interior surface having rifling, an electromagnetic foil forming along a ridge of the rifling.

The application relates to a magnetic confinement fusion plasma temperature diagnosis method, device and equipment, wherein the method comprises the following steps: establishing a neutron yield database, including a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; collecting ion density and total neutron yield of external experimental equipment; assuming that only beam-target reaction exists in an initial stage, obtaining an initial temperature estimation value based on the ion density and the total neutron yield; obtaining first neutron yield and second neutron yield based on the initial temperature estimation value and the ion density, and obtaining theoretical total neutron yield; comparing the difference between the total neutron yield and the theoretical total neutron yield until convergence, obtaining the temperature estimation value as the plasma temperature; and outputting a diagnosis result as an initial temperature of the next moment to realize time sequence evolution analysis. The scheme fully utilizes the thermonuclear fusion and beam-target reaction database, effectively distinguishes the contributions of the two types of reactions to the neutron yield, and avoids the limitations of a traditional single reaction model.

This training device comprises: an input unit that inputs training data, which is experimental data or a numerical calculation result regarding control of nuclear fusion plasma; and a training unit that trains, by means of offline reinforcement learning using the training data, a control model which outputs a control instruction.

This invention relates to the field of controlled nuclear fusion technology, providing a magnetic inertial fusion device and method for accelerating and compressing field-inverted plasma. The device is an integrated linear structure, comprising, from both ends to the middle, a divertor chamber, a field-inverted plasma formation section, a linear acceleration section, a conical tube pre-compression section, and a collision-fusion and magnetic compression region. FRC plasma is formed in the formation section, its axial velocity is increased in the acceleration section, and then pre-compression and stability are improved in the conical tube pre-compression section. After the plasmas at both ends collide and fuse in the middle region, they are magnetically compressed by electromagnetic pulses to reach a medium density (~10²⁴ m⁻³) and fusion temperature, triggering the fusion reaction. The above process can be repeated, the stability of the fusion plasma can be effectively controlled throughout the process, the pulse power heating of the plasma is highly efficient, and the plasma temperature and density can be controlled to simultaneously reach the required fusion conditions; providing an optimal solution for the commercialization of fusion energy.