174 results about "Tokamak" patented technology

The invention discloses an optical mass spectrometer diagnosis technology for distinguishing helium and deuterium Tokamak residual gas by using penning discharge, and the difference between the characteristic spectrums He-I and D-alpha of the low temperature plasma emission spectrums produced by D2 and He discharge is utilized. The D2 and He to be measured are introduced into an ionization chamber, and a penning discharge system installed at one side of the ionization chamber ionizes the gas to be measured to produce low temperature plasma; then the He-I spectral line and D-alpha spectrum generated by the plasma are analyzed, so as to measure the absolute content of the two gases (He and D2). The invention realizes the diagnosis technology for real-time monitoring of the evolution of He and D2 in Tokamak, thus solving the problem that a commercial mass spectrometer cannot distinguish He and D2 due to close molecular mass numbers (He:4.003, D2:4.028). The diagnosis technology provides direct engineering and physical experiences for ITER and possible future in situ measurement of He / D2 on DEMO.

The invention discloses a simulation method for the evolution of an electron cyclotron current profile in a tokamak. In the process of numerically simulating the evolution of the electron cyclotron wave drive current profile in the tokamak device, a drive current source is firstly described by using a Gaussian function; the evolution of the drive current under a specific magnetic field configuration is calculated according to a convection equation determined by a Fisch-Boozer theory; the magnetic field configuration under the correction of the drive current is calculated; the evolution of thedrive current continues to be calculated under the magnetic field configuration; and the simulation effect of long-term evolution is achieved through repeatedly calculating. The method disclosed by the invention has the beneficial effects that the evolution of the electron cyclotron wave-driven current profile under a real three-dimensional magnetic field configuration is realized; the drive current profile can be obtained at any time; in the meanwhile, the spatial distribution situation of the drive current can be more accurately described through the convection equation determined by the Fisch-Boozer theory; the calculation efficiency is high; the numerical stability is strong; and the method is a stable and efficient numerical simulation method.

The invention discloses a low-hybrid-wave antenna phase compensation method. Three lines of main waveguide of an antenna unit respectively comprises a section of linear transitional waveguide with the gradually-widened narrow edge. A main waveguide is divided into N/2 sections of branch waveguide through E face branch waveguide of a first phase shift section, then, the main waveguide is divided into N sections of branch waveguide in a second phase shift section, and N is an even number. Phase shifters are arranged through two methods respectively, and the 180-degree phase difference brought by an output port in the middle line of a mode converter and the phase difference caused by the waveguide length difference which is caused by an antenna port arc notch can be eliminated. The low-hybrid-wave antenna phase compensation method can be applied to the design of a Tokamak low-hybrid-wave multi-junction waveguide antenna and an active and passive staggered multi-junction waveguide PAM antenna of a nuclear fusion experimental device and can be used for eliminating various phase differences of the antennas and improving the coupling performance and current drive efficiency of the antennas and plasmas.

The invention discloses a method for removing hydrogen detained on a first wall in a nuclear fusion device by direct current glow oxygen plasma, which is mainly used for creating optimized wall condition for effective operation of nuclear fusion device plasma physical experiment economy and reducing safely and environment problems due to radioactive tritium detained on the first wall of future device. The inventin is characterized in that according to carbon and hydrogen codeposition characteristic in the device, a plasma auxiliary chemical removing method is used, on a HT-7 superconducting tokmak and a EAST device having similar bit-type with ITER, and first wall temperature of 400-470K, a direct current glow plasma technology is employed, oxygen which is easy to react with carbon and hydrogen is employed to form radio frequency oxygen plasma for removing carbon hydrogen re-deposition layer on the first wall, thereby effectively removing hydrogen detained on the first wall of a device. The invention creates excellent wall condition for re-deposition layer removal on the first wall, reduction of hydrogen detained in the device, particle recirculation lowering and nuclear fusion device high efficiency operation, and reduces safely and environment problems of future nuclear fusion device due to radioactive tritium detained on the first wall.

A microwave-supplying magnetron and an ion burner are provided in an incinerator body, microwave from the magnetron and ion flame from the ion burner are resonated with each other to heat the inside of the incinerator body to high temperature, and wastes in the incinerator body are decomposed and melted by activated ions (+)(-). A tokamak is provided on the outer side of the incinerator body to reflect charged particles (radiation) and electromagnetic waves for focussing to the center of the inside of the incinerator body, thereby increasing an on concentration, a plasma concentration and a decomposing efficiency. Both or one of crystal and an acceptor-level additive are mixed into the furnace wall of the incinerator body.

The invention discloses a method and device for enhancing magnetic disturbance based on gas injection to inhibit an escape current. The method comprises the steps: mounting a gas injection device on aTokamak vacuum chamber; loading gas to be injected into the gas injection device in advance; connecting a trigger control end of a switching valve of the gas injection device to a Tokamak central control system; when a plasma stably operates, controlling the Tokamak central control system not to trigger the switching valve and the gas injection device not to be started; and when the plasma is tobe disrupted, controlling the Tokamak central control system to trigger the switching valve to start the gas injection device, and making the gas injection device inject a gas into the plasma. The gasinjection device comprises a gas storage part, the switching valve and an injection nozzle. According to the method, the gas is injected into the plasma when the plasma is to be disrupted, and the gas entering the plasma disturbs a local current of the plasma to result in magnetic field disturbance, so that the formation of the escape current is inhibited, and the damage of the escape current tothe device is avoided.

The invention belongs to the technical field of nuclear fusion, and particularly relates to a turbulent momentum transport probe array. A rectangular groove at the lower part of a pyrolytic graphite protecting sleeve A is connected with a connecting plate to form a rectangular cavity; a step-shaped cavity fixed connecting piece is arranged at the center of the lower side of the connecting plate; a two-way four-step symmetrical structure is arranged at the upper part of the pyrolytic graphite protecting sleeve A; the middle of the symmetrical structure is high and the two sides of the symmetrical structure are reduced gradually; twenty-one pyrolytic graphite probes are divided into seven rows equally and distributed on steps in parallel; the lower end of each pyrolytic graphite probe is connected with a lead copper tube; the lower ends of the lead copper tubes are collected together by cable leads; the collected cable leads penetrate through a center hole of the connecting plate, and enter the interior of the fixed connecting piece; the lower ends of the cable leads are connected with movable plugs; and insulation sleeves are arranged in the rectangular cavity formed by the pyrolytic graphite protecting sleeve A and the connecting plate, and arranged among the lead copper tubes. With the adoption of the probe array, a macroparameter of plasma of an HL-2A tokamak device can be measured in a discharging process.

The invention discloses a high-frequency magnetic probe diagnosis system for measuring radio frequency wave characteristics. The measuring system comprises a vacuum coaxial electrode, a high-frequencymagnetic probe, a power divider, a detector, a phase discriminator and a signal acquisition system, the vacuum coaxial electrode is used for transmitting radio frequency signals from the Tokamak to the outside of the Tokamak; the high-frequency magnetic probe is used for coupling the radio-frequency signals; the power divider is used for distributing the voltage probe and current probe signals into two paths with equal amplitude and equal phase; the detector is used for detecting the peak-to-peak value of the voltage probe and current probe radio frequency signals, and the result is output bya direct-current signal; the phase discriminator detects the phase difference between the voltage probe and current probe signals, and the result is output by a direct-current signal. The signal acquisition system stores the collected voltage signals to a computer.

The present invention discloses high power continuous wave DCN laser. It contains discharge tube, anode, cathode, vacuum-pumping interface and inspiration interface on discharge tube, oil cooling jacket, waveguide type resonant cavity adopting plane cavity shape, plane reflection mirror, metallic nickel silk screen having tungsten filament, adopting x quartz plate sealing for anode end discharge tube laser output window, working medium being deuterate methane, nitrogen gas and deuterium gas or helium gas mixed gas. Said invention can continue steady operate for 168 hr. under lambda=194.7 micrometer output power about 150 mw condition, providing reliable plasma electron density measurement.

The invention discloses a phase-measuring device and identification method to entrance Tokamak low clutter antenna phase. That is to connect a dual directional coupler respectively at the root of every klystron output waveguide transmission line and near the antenna. Each dual directional coupler microwave signal is separated into two parts through filter and two straight power splitters respectively access Module A, B input. Phase two modules used to work, A module will phase output phase voltage curves of the same phase of the two phase corresponding phase combined output phase voltage module B identify a phase value. The invention measures and phases out amount of regulation quickly and accurately when Tokamak system sends the 2.45 GHz microwave signal to antenna phase entrance, provides accurate feedback phase of the phase control, provide a reliable technical support for studying microwave plasma coupling efficiency.

A high-power continuous wave klystron for Tokamak device is formed by three portions: the first portion is an electronic focusing system which comprises a negative electrode, a control electrode and a positive electrode and the like, where electron beams emitted from the negative electrode are converged by the control electrode and the positive electrode, then, form a round electron beam after being subjected to high voltage acceleration, and reach a beam-wave interaction system of the klystron; the second portion is a high-frequency beam-wave interaction system of the klystron, the high-frequency beam-wave interaction system being formed by a cylindrical reentrant resonant cavity comprising an input cavity, buncher cavities and an output cavity, wherein the high-frequency beam-wave interaction system realizes improvement of power capacity, efficiency and gain effectively, and high-frequency microwave produced in the cavity is output through an output cavity waveguide; and the third portion of a collector, wherein the collector helps to collect the energy of electron beam in beam-wave interaction. The high-power continuous wave klystron is simple and easy to carry out; the high-power continuous wave klystron has the advantages of easy processing, small process processing difficulty, high efficiency and high gain and the like; and the high-power continuous wave klystron can work more stably and reliably.

The invention relates to the field of nuclear fusion and discloses a method for measuring an ablation resistance characteristic of materials. According to the method, the laser-induced breakdown spectroscopy (LIBS) and the quartz crystal microbalance (QCM) are combined, wherein the LIBS is used for diagnosing types of species generated by ablation and the percentage of all the species; the QCM is used for calculating total ablation amount, and then, measuring results of the LIBS and the QCM are combined to obtain the ablation rate of all components. According to the method for measuring the ablation resistance characteristic of the materials, by combining the LIBS and the QCM, defects that LIBS quantitative analysis is comparatively difficult and substance distinguishing cannot be performed by the QCM are remedied; the types of species generated by the ablation and the percentage of all the species are diagnosed by using the LIBS, and the total ablation amount is calculated by the QCM; and then, the measuring results of the LIBS and the QCM are combined to obtain the ablation rate of all the components. A feasible detection means is realized for evaluating whether an already used material is suitable for Tokamak stable operations or not and seeking a first wall material which is suitable for the Tokamak stable operations.

This invention discloses a method for measuring corona current in tokmak device and its device, characterized in: equipping interconnect screw coil with high frequency response in tokmak device vacuum case inwall, via inducted current of screw coil, attaining changes of vacuum inner magnetic field, based on these, via high temperature plasmas, round vertical field magnet, pole field magnet and vacuum case body in the tokmak device, testing the screw coils to attain corona current, and the non-uniformation of current distribution along ring direction.

The invention discloses a method applicable to a fusion reactor for triggering a high-frequency edge localized mode by low-hybrid-wave modulation, which is characterized in that the current density orpressure intensity distribution of a stylobate region of the fusion reactor is directly or indirectly changed by using high-frequency, high-power and low-hybrid-wave modulation injection under the parameter background that a low-frequency large-amplitude edge localized mode breaks out in the operation of a high confinement mode of a Tokamak fusion reactor, a high-frequency edge localized mode istriggered, the amplitude of the edge localized mode and the harm brought about by the edge localized mode for a wall material of the fusion reactor are reduced. The method disclosed by the invention has flexibility in technical adjustment and adaptability for plasma parameter changes, and has little disturbance to plasma discharge during steady-state operations of the fusion reactor.

The invention discloses a foreign particle concentration measuring system for a J-TEXT Tokamak device. The foreign particle concentration measuring system comprises an X-ray optical path module, an X-ray detection module, a pulse shaping amplification module and an MCA data processing module. When the Tokamak device is cracked, a foreign gas is injected in order to suppress high-energy high-speed escape electrons, foreign particles may generate radiation and the impurity concentration is calibrated by measuring the impurity radiation intensity. Because a radiation energy pulse signal is weak, a high-sensitivity detector is used to detect the pulse signal and the high-gain pulse shaping amplification module is used to shape and amplify the pulse signal in order to output a voltage pulse signal with amplified amplitude. The MCA data processing module, according to the collected voltage pulse signal, performs energy spectrum analysis. Because different impurities have different radiation pulse peaks, the concentration of the various impurities can be determined according to the energy spectrum.

The invention discloses a high-temperature superconduction cable for strong magnetic field and fusion reactor tokamak superconduction magnet. The high-temperature superconduction cable comprises a support structure, wherein a plurality of grooves are formed in the support structures in an axial direction, semi-circular low-temperature cooling grooves are formed in the bottom and a side wall of each groove, a high-temperature superconduction strip stack is fixedly welded with the interior of each groove by a heat conduction and electric conduction welding material, a filler is arranged on the high-temperature superconduction strip stack and is used for fixing the strip stack, a central cooling hole is formed in the center of the support structure, and a protection shell sleeves an outer side of the support structure. Two cooling modes of conduction cooling and direct cooling are employed. The cable employs a spirally-twisting high-temperature superconduction stack to eliminate the anisotropy of the high-temperature superconduction strip, the mechanical property of the cable is improved, and the stability of the cable under a large-current and complicated strong magnetic field fusionenvironment is improved.

The invention discloses a hard X-ray flux detection system of a J-TEXT Tokamak device. The hard X-ray flux detection system comprises a hard X-ray detection module, a detection circuit and an AD data acquisition module; the J-TEXT Tokamak device generates a large number of high-speed escape electrons when disruption is operated; the high-speed escape electrons bombard the material of the first wall of the device so as to directly damage the material; great importance should be attached to the density monitoring of the escape electrons; when the escape electrons damage the first wall, thick target bremsstrahlung occurs between the escape electrons and the material, and hard X-rays are generated, and the energy of the hard X-rays can be up to 0.5 to 10MeV; the more escape electrons strike the wall of the device, the higher the energy of the generated hard X-rays is, and the higher pulse voltage outputted by the detector is; hard X-ray optical signals are converted to pulse voltage signals through the hard X-ray detection module; the peak signals of the pulse signals are detected by the detection circuit; the peak signals are transmitted to a computer terminal through the data acquisition card; the computer terminal stores the peak signals; radiation intensity can be determined; and since the radiation intensity is proportional to the amplitude of the pulse signals, the distribution condition of the escape electrons can be obtained.

The invention belongs to the technical field of Tokamak device, particularly relates to a scanning probe system on a high field side of a Tokamak device, which solves the measurement problem of plasma parameters at the edge on the high field side of the Tokamak device. A shaft is assembled on a fixed bracket through a bearing and a bearing sleeve; a coil, a coil framework and a probe fixed bracket connecting pipe are assembled on the shaft respectively; the coil and the plane surface of the coil framework are mutually perpendicular to the probe fixed bracket connecting pipe in the axial direction; a probe fixed bracket is arranged on the probe fixed bracket connecting pipe; a probe socket is arranged on the probe fixed bracket; probes are arranged on the probe socket and divided into two groups with one group arranged in a circular direction and another group arranged in an electrode direction; and lead wires connected with the probes are led out through the probe fixed bracket connecting pipe. In the scanning probe system provided by the invention, the probes are made of pyrolysis graphite material, and digital raster displacement is adopted for automatic measuring and controlling the movement displacement; and the temperature, the density, and the distribution of electric potential and the field of the electronics at the edge, which are vital parameters in the study of edge physics, can be simultaneously measured within one discharge of the controlled nuclear fusion study device.

The invention provides a device for cleaning a first mirror for a tokamak device by a direct-current cascade arc plasma torch. The device for cleaning the first mirror for the tokamak device by the direct-current cascade arc plasma torch comprises a cascade arc plasma torch generation system, a cooling water supplying system, a supporting system and a reflectivity detection system, wherein the cascade arc plasma torch generation system comprises a vacuum chamber, a cascade source, a direct-current power supply, a vacuum unit, a gas supply unit and a cooling unit; the cascade source is arranged at one end of the vacuum chamber; the direct-current power supply is electrically connected with the cascade source; the gas supply unit is connected with the cascade source through a pipeline; the vacuum unit is connected with the vacuum chamber; the cooling unit is arranged in the cascade source. The device for cleaning the first mirror for the tokamak device by the direct-current cascade arc plasma torch is simple, reasonable and compact in structure; the device is based on a direct-current cascade arc plasma torch technique; on the premise that an impurity is not introduced, the large-area and uniform cleaning of an impurity sedimentary formation on the surface of a sample of the first mirror can be realized; the impurity sedimentary formation is removed quickly.

The invention discloses a Tokamak plasma disruption energy processing device and processing method. The Tokamak plasma disruption energy processing device comprises a voltage dependent resistor, a pulse capacitor unit, a resistance unit, an invert unit and a control unit; the voltage dependent resistor, the pulse capacitor unit and the resistance unit are parallelly connected in sequence between the positive pole and the negative pole of a direct current bus, and the positive pole and the negative pole of the pulse capacitor unit and the positive pole and the negative pole of the direct current bus are correspondingly connected; the positive pole of an input end of a direct current side of the invert unit is connected with the positive pole of the direct current bus, and the negative pole of the input end of the direct current side of the invert unit is connected with the negative pole of the direct current bus. The Tokamak plasma disruption energy processing device and processing method are mainly applied to the controllable nuclear fusion Tokamak plasma disruption energy processing, a multiprocessing function of processing energy storage, energy absorption, energy consumption and energy feedback recycle is achieved, the plasma disruption energy transmitted by a plasma coupled coil can be effectively absorbed and processed, and the Tokamak plasma disruption protection and the energy recycling are achieved.