73 results about "Magnetic confinement fusion" patented technology

A laser inertial-confinement fusion-fission energy power plant is described. The fusion-fission hybrid system uses inertial confinement fusion to produce neutrons from a fusion reaction of deuterium and tritium. The fusion neutrons drive a sub-critical blanket of fissile or fertile fuel. A coolant circulated through the fuel extracts heat from the fuel that is used to generate electricity. The inertial confinement fusion reaction can be implemented using central hot spot or fast ignition fusion, and direct or indirect drive. The fusion neutrons result in ultra-deep burn-up of the fuel in the fission blanket, thus enabling the burning of nuclear waste. Fuels include depleted uranium, natural uranium, enriched uranium, spent nuclear fuel, thorium, and weapons grade plutonium. LIFE engines can meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the highly undesirable stockpiles of depleted uranium, spent nuclear fuel and excess weapons materials.

The invention discloses a plasma device with a double-hollow cathode and a double-hollow cathode and applications. The device comprises filaments, a hot cathode, an anode, a double-hollow cathode, a cold cathode, a vacuum chamber and a magnet, wherein the double-hollow cathode comprises an outer wall and a lining layer and is of a double-layer structure. Due to the double-layer hollow cathode structure, the lining layer is easy to disassemble and change, so that the lining layer can be observed and analyzed properly, and simultaneously, the demand that single or multiple types of metal plasma is / are generated by a sputtering cathode in an arc chamber. On one hand, according to the plasma device, a double-hollow cathode plasma sputtering mode controlled by a magnetic mirror field is adopted for generating high-density plasma with the single or multi-element metal and plasma flow with high efficiency, and the plasma device is used for the modification on the surface of irradiation material of the metal plasma and research on the high-purity high-flow metal ion beam; and on the other hand, the plasma device is combined with various surface analyzing technologies to observe and analyze the inner surface of the double-hollow cathode, and used for researching the mutual action between the plasma and a machine wall in magnetic confinement fusion.

Disclosed is a device comprising a chamber enclosed by walls about a central axis. The chamber has an inner radius and an outer radius relative to the central axis and is configured to magnetically contain a core plasma. The device is further comprised of a divertor plate configured for receiving exhaust heat. The divertor plate has a divertor radius relative to the central axis. The divertor radius is greater than or equal to the sum of a plasma minor radius and a major radius of the peak point closest to the corresponding divertor plate. The device can be used for containing a fusion plasma, as a compact fusion neutron source, or as a compact fusion energy source. Methods of exhausting heat from such a device when plasma is present therein are also described. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

The invention discloses a fast electron measurement probe system suitable for magnetic confinement plasma. The fast electron measurement probe system comprises an insulating shell, a fast electron probe assembly, a Langmuir probe assembly and a ceramic base. The insulating shell is formed by processing high-temperature-resistant boron nitride, the ceramic base is made of machinable ceramic, a plurality of Langmuir probes are distributed at the front end of the probe system, and a plurality of fast electron probes are uniformly and symmetrically distributed on two side surfaces of the probe system and are used for collecting electron current. The fast electronic probe and the Langmuir probe respectively comprise a graphite probe, a copper binding post, a wire and the like, the graphite probes and the copper binding posts are connected through threads, the copper binding posts and the wire are connected through crimping pliers in a crimping mode, connection is reliable, and high temperature resistance is achieved. According to the fast electron probe, the radius of an electron Larmor in magnetic confinement plasma is far smaller than that of ions, and the ions can be effectively repelled by setting the width and the depth of a small hole to collect electrons. The system can work in a high-temperature environment in the magnetic confinement fusion device, and is stable in mechanical performance, reliable in signal, high in spatial resolution and small in occupied space.

Disclosed is a device comprising a chamber enclosed by walls about a central axis. The chamber has an inner radius and an outer radius relative to the central axis and is configured to magnetically contain a core plasma. The device is further comprised of a divertor plate configured for receiving exhaust heat. The divertor plate has a divertor radius relative to the central axis. The divertor radius is greater than or equal to the sum of a plasma minor radius and a major radius of the peak point closest to the corresponding divertor plate. The device can be used for containing a fusion plasma, as a compact fusion neutron source, or as a compact fusion energy source. Methods of exhausting heat from such a device when plasma is present therein are also described. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

The invention discloses a magnetic control powder combustion-type plasma flow calculation method, which belongs to the field of magnetic confinement plasma, and comprises step S1 of establishing a magnetohydrodynamic model, solving a fluid mechanics equation and an electromagnetic confinement system equation that control plasma motion through coupling, and researching an interaction law of a flowfield and an electromagnetic field in the plasma; step S2 of performing numerical calculation; and step S3 of verifying a calculation program, and analyzing and verifying the calculation program fromdifferent angles respectively. The calculation method of the invention is more scientific and reasonable. An adaptive magnetohydrodynamic model is established regarding the flow problem of the magnetic confinement powder combustion-type plasma. An induction magnetic field equation method is adopted to couple and solve an N-S equation group containing an electromagnetic source item and the electromagnetic confinement system equation. Meanwhile, a k-epsilon turbulence equation is modified electromagnetically. Further, on the basis of determining a boundary condition, the interaction law betweenthe flow field and the electromagnetic field and a turbulence structure in the plasma are predicted.

The invention discloses a measurement method for the two-dimensional distribution of deuterium or tritium detained on surface of a first Tokamak wall material, which is used for studying retention characteristics of deuterium (tritium) elements on the surface of the first wall material of a magnetic confinement fusion device so as to obtain the two-dimensional distribution of the deuterium (tritium) elements in a tiny area on the surface of the wall material. The measurement method is characterized in that: two high-power tunable pulse laser beams are respectively used for disaggregating chemical bonds (desorption) of C-H and C-D through resonance and for ionizing H atoms and D atoms through resonance to effectively produce H<+> ions and D<+> ions, and deuterium (tritium) ions are detected by using the mass spectrum of the time of flight. A microscope / camera system is used for observing a detected sample area, and the two-dimension analysis of samples is realized through a precise two-dimensional electric platform; moreover, when the measurement method is adopted, the distribution condition of the deuterium (hydrogen, tritium) elements on the surface of the first wall material canbe effectively measured at a high speed with high sensitivity and high resolution, and a basis is provided for the detailed study of the surface retention characteristics of the deuterium (tritium).

The invention discloses dual-layer-flow liquid first wall cladding applicable to a magnetic confinement fusion reactor. The cladding structurally comprises a vacuum chamber, liquid metal injection pipes at the top of the vacuum chamber, an outer cladding back wall adopting a spiral insulated runner structure, an inner cladding back wall and a bottom liquid metal discharge structure. In order to solve problems of the MHD (magnetohydrodynamics) effect, the thinning effect and the like encountered by a liquid first wall during application to the fusion reactor, a special structural design is adopted: for inner cladding, the inlet injection pipes inject a liquid metal downwards from the top of the vacuum chamber along the inner cladding back wall; for outer cladding, the liquid metal is injected in the circumferential direction of the vacuum chamber, is closely attached to the outer cladding back wall and flows downwards under the effect of the centrifugal force produced due to the inertia, and overwhelms a spiral insulated runner arranged on the outer cladding back wall, so that a circumferential flow in the insulated runner and a free surface flow outside the runner are formed. The liquid metal finally flows into the bottom liquid metal discharge structure and is applied to heat transfer, tritium extraction and recycling, and the problems of the MHD effect and the thinning effect can be effectively solved.

The invention discloses a method and a system scheme for constructing plasma capable of realizing a magnetic confinement fusion reaction by heating a mixture consisting of lithium, tritium and deuterium in a magnetic confinement device by utilizing neutrons. The neutrons required for heating the plasma are provided by performing doubling, moderating and reflecting on an external neutron source or fusion neutrons generated by a fusion reaction in a device through a cladding on the container wall of the magnetic confinement device. The lithium in the plasma is obtained by injecting lithium metal nano-particles or lithium deuteride projectiles. According to the method and the system scheme, the plasma is heated by MeV-level high-energy tritium particles and helium particles generated by a fission reaction caused by bombarding the lithium in the plasma by the neutrons. The plasma formed and maintained by the heating method is mainly deuterium lithium plasma. According to the heating method-based magnetic confinement fusion device, the problem about tritium self-sustaining is not required to be considered, the design of a fusion reactor is greatly simplified, and the economical efficiency of the fusion reactor is greatly improved.

The invention provides a preparation apparatus of a microspheric polymer coating. The apparatus comprises an air inlet pipe, a radio shielding case, an inductance coil, a quartz resonant cavity and a vacuum chamber. The quartz resonant cavity is positioned in the inductance coil which is positioned inside the radio shielding case. The air inlet pipe is connected with the quartz resonant cavity which is connected with the vacuum chamber. A sample rack, a sample lifting platform and a knocking stick are arranged inside the vacuum chamber. The preparation apparatus is applied in the preparation of a pellet ablation-layer material in the field of initial confinement fusion, and has the characteristic of realizing controllable thickness of the microspheric polymer coating, single layer of the microspheric polymer coating, multilayer doping and the like.

The invention discloses an ICF (inertial confinement fusion) cryogenic target device and an ICF shielding cover opening speed optimization method. The ICF cryogenic target device comprises a thermal radiation shielding cover; a vacuum region is defined in the thermal radiation shielding cover; a thermal mechanical structure is arranged in the vacuum region; the outer sides of the upper part and lower part of the thermal mechanical structure are provided with two cold rings respectively; a gold cavity is closely attached to the inside of the thermal mechanical structure; the gold cavity is filled with a filling gas; a cryogenic target pellet is fixed to the center of the gold cavity through a supporting film; and the thermal radiation shielding cover is composed of two detachable parts which are connected through a shielding cover connection structure. The ICF shielding cover opening speed optimization method of the invention includes the following steps that: the radiation temperatureof the thermal radiation shielding cover is determined; a model is established according to the radiation temperature and the specific condition of the cryogenic target; the opening mode of the thermal radiation shielding cover is determined; and different shielding cover opening speeds are provided, and an optimized opening speed and corresponding time are obtained.

The invention relates to a preparation method of a superconducting D-type coil for magnetic confinement fusion, which comprises the following steps: A, preparation of a coil framework: processing a high-strength metal circular tube into a D-type shape to obtain the coil framework; B, coil winding: spirally winding a plurality of high-temperature superconducting strips on the coil framework side byside to form a plurality of coil winding layers, and staggering the high-temperature superconducting strips of the adjacent winding layers by a distance of 1 / 2-1 / 3 of the width of the strips; and obtaining a superconducting D-type coil blank; C, coil curing: performing epoxy resin impregnation curing or paraffin impregnation curing on the superconducting D-type coil blank to obtain the cured superconducting D-type coil; and D, armor reinforcement: wrapping the cured superconducting D-type coil with a wrapping sleeve composed of an upper half tube and a lower half tube, and performing impregnation and curing again to obtain the superconducting D-type coil. The superconducting D-type coil prepared by the method is high in percent of pass, good in current-carrying performance and high in mechanical strength, and can generate a stronger strong magnetic field in a large space.

The invention discloses a method for cleaning a first wall of a magnetic confinement fusion device by using a high-frequency field. The method is implemented by the steps of: (1) previously filling gas of 0.1-10 Pa in a vacuum chamber of the magnetic confinement fusion device; (2) arranging a high-frequency antenna in the vacuum chamber of the magnetic confinement fusion device, then taking the vacuum chamber of the magnetic confinement fusion device as a negative electrode and the high-frequency antenna which extends into the vacuum chamber of the magnetic confinement fusion device as a positive electrode, and applying the high-frequency field with voltage of 3-5 KV, frequency of 20-50 KHz and power of 2-10 KW between the negative electrode and the positive electrode; and (3) breaking down gas under the action of ionization of the high-frequency field and generating stable high-frequency plasma discharge, performing effective bombardment on the first wall of the vacuum chamber of the magnetic confinement fusion device, and cleaning the first wall after discharge cleaning of 1-10 hours. Through the method, the cleaning efficiency can be doubled.

The invention belongs to the magnetic confinement fusion technical field and concretely relates to a Tokamak tripod divertor magnetic field configuration construction method. According to the method,distances between the geometric center position of a first poloidal field coil and a first X point, between the geometric center position of a second poloidal field coil and the first X point, betweenthe geometric center position of a third poloidal field coil and the first X point and between the geometric center position of a fourth poloidal field coil and the first X point are set to be 1-1.5a, 1.5-3a, 1.5-3a and 1.5-2.0a respectively, wherein a is the minor radius of a plasma. The method solves the technical problems that the target plate heating area of a common divertor of a conventional Tokamak magnetic confined plasma experiment apparatus is small and cooling of a target plate of the divertor faces huge technical challenges in a high heating condition. A constructed tripod divertor magnetic field configuration can alleviate heat load of a target plate and improve compatibility of running of a divertor and running of a core high heating plasma. The performance of dust removal and impurity shielding characteristics are better exhibited, and requirements of coil current strength and coil arrangement complexity are reduced for an advanced divertor configuration.

The invention discloses a novel resonance magnetic disturbance coil suitable for a magnetic confinement fusion device. Two groups of coils are uniformly distributed in the circumferential direction, and each group of coils is positioned on the middle plane of a low field side. Each group of coils comprises two closed loops, a circuit in each closed loop is provided with a plurality of turns of coils which are symmetrical up and down, and a plurality of current interfaces are arranged. A flexible connection mode is achieved, and disturbance magnetic fields of different spectrum types can be generated after the coils are powered on. The coils adopt a hollow water-cooling pipeline design, and can stably work for a long time under the condition of large current. According to the invention, theprinciple of an external magnetic disturbance control boundary local mode is utilized, and a local disturbance magnetic field with high polar modulus and wide circumferential modulus spectral patterncharacteristics and enough strength is generated through the coils, so that the disturbance of the coils to core plasma is reduced, the active control of the resonance magnetic disturbance coil is effectively broadened, and the working window of a boundary local mode is suppressed. The device can work on a magnetic confinement nuclear fusion device, is simple in structure, easy to install, smallin occupied space and reliable in performance, and is an important scheme for enriching boundary local mode control.

The invention discloses a bidirectional power source of a small spherical Tokamak ohm magnet, belonging to the technical field of magnetic confinement fusion. The bidirectional power source consists of two capacitor groups, four IGBT (Insulated Gate Bipolar Transistor) switch modules, two diodes, a large-power non-inductive resistor and a first magnetic field coil. The bidirectional power source disclosed by the invention has the advantages that by using the four parallel-connected IGBT switch modules as a large-current (100 kA) switch, the bidirectional power source has the characteristics of simple and compact structure, convenience for driving, reliability in working and free maintenance; a waveform has no need of being adjusted by changing duty ratio, and the interference brought by frequently switching with a large current is eliminated; and the technical requirement on parallel connection of the IGBT switch modules is greatly reduced by only switching on and off the four IGBT switch modules once, so that the reliability is further improved.

The invention relates to the field of nuclear fusion and optical diagnosis and discloses a method for detecting instant temperature of a graphite tile of a partial filter of a magnetic confinement fusion device. The technical schemes includes that when the magnetic confinement fusion device works normally, terahertz waves are perpendicularly injected into the graphite tile from a position outside a window, and a probe is used for measuring and recording a terahertz time-domain spectrum Omega<T>(t) reflected by the graphite tile under working temperature. The time-domain spectrum is analyzed and processed and transformed in Fourier transformation in an effective frequency domain to obtain a frequency domain spectrum F<T>(omega) under the working temperature. At the moment, data automatically selects a characteristic spectral line, reads positions of the characteristic spectral line in a data base under calibrated temperature, frequency shift amount is obtained by comparing the two positions, a functional relationship of frequency shift amount - temperature of the data base is compared with the frequency shift amount, and the instant temperature is then calculated, outputted and led to a computer system to be stored. According to the method for detecting the instant temperature of the graphite tile of the partial filter of the magnetic confinement fusion device, technology of reflecting the terahertz time-domain spectrum is adopted, the thermal shock instant temperature of the graphite tile of the partial filter of the magnetic confinement fusion device can be detected online, synchronously, and without contact or damage.

The present invention is composite doped graphite material and its preparation. It is prepared by mixing and crushing raw coke powder and asphalt with self-sintering function, adding B4C powder, Si powder and Ti powder, ball milling sieving, hot pressing to form and graphitization. Compared with high density and high strength pure graphite with thermal conductance of 70-80 W / m.K, the composite material has thermal conductance as high as 150 W / m.K, five times higher chemical sputtering resistance, raised tension strength, thermal shock resistance and vacuum performance, and excellent comprehensive performance. It may be used in large superconductive magnetic constraint fusion reactor and aeronautic and astronautic technological fields.

The invention discloses a high-current-carrying high-temperature superconducting composite conductor based on a sectioned stacking structure. The composite conductor is composed of a stainless steel armor with a square outer part and a round inner part and four high-temperature superconducting cables with the same model. The four high-temperature superconducting cables are structurally composed ofan insulating sheath, an aluminum sheath, four quarter-ring-shaped copper matrixes with square grooves formed in the outer sides and four sets of yttrium-barium-copper-oxide high-temperature superconducting strip stacks embedded into the square grooves of the copper matrixes respectively. The copper matrixes, the yttrium-barium-copper-oxide high-temperature superconducting strip stacks and the aluminum sheath are fixed through soldering tin; and equidistant cooling holes are formed in the aluminum sheath to enhance the cooling capacity of the conductor. The composite conductor is compact in structure, high in current-carrying capacity under the condition of a high background magnetic field, high in anti-interference capacity, high in stability margin and suitable for various high-field superconducting cable application scenes including magnetic confinement fusion reactor superconducting magnets.

The invention discloses an ICF (inertial confinement fusion) target assembly parameter measuring multi-freedom degree precision motion platform device. The ICF target assembly parameter measuring multi-freedom degree precision motion platform device comprises four parts, namely an ICF target parameter measuring three-dimensional translation system, an ICF target parameter three-dimensional monitoring system, an ICF target attitude double-rotation precision adjustment system and a vibration isolating platform for bearing the former three systems, wherein the ICF target parameter measuring three-dimensional translation system, the ICF target parameter three-dimensional monitoring system and the ICF target attitude double-rotation precision adjustment system are mounted on the vibration isolating platform in a delta form. Through combination with a high-precision air-floating guide rail and an air-floating shaft system and structural optimization and integration, high-precision adjustmentof ICF target space attitude is achieved; the designed motion platform with the ability of outputting target coordinate parameters completes precision adjustment and control of the overall target space attitude through cooperation with other projects, so that measurement of geometric quantities such as the size and the shape accuracy of microspheres, microcylinders and ICF target assembly parameters can be achieved.

The invention belongs to a magnetic confinement plasma diagnostic device, and particularly relates to a high-precision magnetic field inclination angle measuring system applied to a magnetic confinement fusion device. The high-precision magnetic field inclination angle measuring system comprises a neutral beam injection system which is installed in a fusion plasma. The external part of the fusion plasma is provided with a front-end optical lens which is connected with an optical modulation system. The optical modulation system is connected with gratings via optical fibers. The gratings are opposite to optical fiber arrays and a photoelectric conversion system. The optical fiber arrays and the photoelectric conversion system are connected with a phase-locked amplifier. Meanwhile, the optical modulation system is connected with the phase-locked amplifier so as to provide reference signals to the phase-locked amplifier. The phase-locked amplifier is connected with a data acquisition and control computer. The advantages of the high-precision magnetic field inclination angle measuring system are that reliability is great and measuring precision is quite high so that the high-precision magnetic field inclination angle measuring system can be applied to measurement of a plasma magnetic field deflection angle under the weak stark effect and can also be applied to high-precision and high-speed measurement of other linearly polarized light polarization direction.

The invention discloses a real-time lithiation wall processing system used for improving the wall conditions of plasma. The system comprises an evaporator, a baffle and control system and a corrugatedpipe conveying system, the baffle and control system comprises a rotary baffle; the baffle is arranged at an evaporation outlet of the evaporator; a rotary shaft of the baffle penetrates through theevaporator and extends to the outer end portion; a linear guide-in device is installed at the other end of the rotary shaft; the lower end of the linear guide-in device is connected to a nitrogen cylinder through a pipeline; the corrugated pipe conveying system comprises a supporting pipe installed on the rotary shaft at the rear end of the evaporator in a sleeving mode; the front end of the supporting pipe communicates with the evaporator; the rear end portion of the supporting pipe is sleeved with a corrugated pipe; and a gate valve and a lithium containing chamber are installed at the position, at the front end of the corrugated pipe, of the supporting pipe. The first wall surface is coated with lithium in real time during plasma discharging, the improvement of the plasma performance isachieved rapidly, economically and effectively, and the long-pulse and high-power plasma discharging of a magnetic confinement fusion device is conducted advantageously and successfully.

The invention discloses a polar fast electron measurement probe system suitable for magnetic confinement plasma. The polar fast electron measurement probe system comprises an insulating shell, fast electron probe assemblies, a Langmuir probe assembly, a ceramic base and a graphite shell. The insulating shell is made of high-temperature-resistant boron nitride, and the ceramic base is made of machinable ceramic. The probe assembly comprises a graphite probe, a copper binding post, a wire and other components, the graphite probe is in threaded connection with the copper binding post, and the copper binding post is in tin soldering connection with the wire or is in press connection with the wire through crimping pliers. The fast electron probes are uniformly and symmetrically distributed in the polar direction, and fast electron components from different directions can be measured. The graphite probes of the fast electron probes are located in the small holes and are applied with positivebias voltage. The radius of the electron Larmor in the magnetic confinement plasma is far less than that of ions, the ions can be effectively repelled by setting the diameter and the depth of the small hole so as to collect electrons. The system can work in the high-temperature environment in the magnetic confinement fusion device, and is stable in mechanical performance, reliable in signal, highin spatial resolution and small in occupied space.

The invention relates to the field of energy resources, particularly to a continuous molten metal film generating device and method under a high-intensity magnetic field. The continuous molten metal film generating device includes a plurality of mutually overlaid liquid film generation subunits made of insulating materials and unequal in length, wherein from the top layer to the bottom layer, the conveyed quantity of metal liquid is gradually increased; in the adjacent two liquid film generation subunits, the metal liquid transmitted from the tail end of an output passage of the lower liquid film generation subunit is combined with the metal liquid transmitted from the flowing area of the upper molten metal film, so as to form a continuous molten metal film. According to the continuous molten metal film generating device and method under a high-intensity magnetic field, provided by the embodiment of the invention, metal liquid of all the layers passing by the output passages is joined with the metal liquid of the upper layer, and the flowing area formed by the flowing molten metal film of metal liquid is shorter, so that an integral, stable and continuous molten metal film is formed, and the functions of taking heat and impurities away and the like of the molten metal film in a practical magnetic confinement fusion reactor device are realized.

The invention discloses a magnetic confinement device and method of CO2 laser beam bunching, and relates to the technical field of laser measurement. The device comprises a four-dimensional motion platform (101), a magnetic confinement device body and a facula dimension sensor (109) in sequence, the four-dimensional motion platform (101) is used for containing a CO2 laser (102), the magnetic confinement device body is used for laser beam bunching, and the facula dimension sensor (109) is used for detecting laser beam bunching performance. The magnetic confinement device body mainly comprises a mutual-exclusion magnetic confinement body (108) capable of rotating at high speed, the mutual-exclusion magnetic confinement body (108) is composed of a plurality of pairs of magnetic bodies with opposite polarities, a magnetic cavity (107) is formed in the middle of the mutual-exclusion magnetic confinement body (108), and laser beams emitted by the CO2 laser (102) can penetrate through the magnetic cavity (107). When a laser penetrates through the magnetic cavity, due to the fact that light ray deflection occurs to the laser in a mutual-exclusion magnetic field, the peripheral light rays of the laser beams deflect towards the center, and therefore the aim of improving the laser beam bunching performance is achieved.

The invention discloses a preparation method of a plastic scintillator optical fiber array. The method includes the steps that styrene is utilized as a polymer matrix monomer, 2,5-diphenyloxazole and1,4-bis[2-(5-phenyl) oxazolyl] benzene are utilized as a scintillation matrix, and a melt spinning technology is adopted to prepare the plastic scintillator optical fiber array with good light-emitting performance. According to the preparation method, by adjusting the mass fraction of 2,5-diphenyloxazole and 1,4-bis[2-(5-phenyl) oxazolyl] benzene and controlling the melt spinning process parameters, the plastic scintillator optical fiber array with good light-emitting performance is obtained. The plastic scintillator optical fiber array with good light-emitting performance prepared through thepreparation method can be applied in the field of physical process diagnosis of inertial confinement fusion (ICF), neutron / neutrino detection, nuclear medical imaging, environmental detection and thelike.

The invention discloses a system and method for simulating tritium circulation of a magnetic confinement fusion reactor, and the system comprises a reactor core reaction module, a reactor core tritiumfuel recovery module, a reactor core tritium fuel purification processing module, and a reactor core tritium fuel support module, which form a tritium fuel internal circulation system. The reactor core reaction module, the reactor core tritium fuel multiplication module, the cladding fuel purification treatment module and the reactor core tritium fuel support module form a tritium fuel outer circulation system; and the tritium fuel internal circulation system and the tritium fuel external circulation system work based on a preset mass balance equation set so as to realize reactor core tritiumfuel self-sustaining. Based on the mass balance equation set, unburned tritium fuel is recovered through the reactor core tritium fuel recovery module, and tritium fuel is multiplied through the reactor core tritium fuel multiplication module, so that reactor tritium self-sustaining is realized, and the reactor tritium self-sustaining method can be widely applied to the technical field of fusion.

The invention belongs to the field of magnetic confinement controlled nuclear fusion plasma diagnosis, and relates to a terahertz microwave interference array for measuring a two-dimensional electron density profile based on a time delay method, which is an important technical method for measuring the electron density of magnetic confinement plasma. An adopted device mainly comprises a crystal oscillator, a six-centimeter device, a dot frequency source, a terahertz frequency multiplier, an integrated unit composed of a two-centimeter device, a programmable microwave switch, a frequency mixer, an amplifier, a detector and a central processing unit, a microwave waveguide, a terahertz phased array antenna and the central processing unit. According to the array disclosed by the invention, time-sharing measurement of a plurality of spatial positions can be realized by arranging a plurality of terahertz phased array antennas capable of flexibly adjusting emission angles and a programmable microwave switch in a magnetic confinement fusion device, and then a two-dimensional measurement electron density profile is obtained by utilizing a fast numerical inversion algorithm; and the time delay method is especially suitable for large-scale magnetic confinement fusion devices in the future.

The invention belongs to the magnetic confinement fusion design technical field and concretely relates to a Tokamak hybrid divertor magnetic field configuration construction method. According to the method, a first poloidal field coil, a second poloidal field coil and a third poloidal field coil are arranged on a strong field side, and distances between the geometric center position of the first poloidal field coil and a first X point, between the geometric center position of the second poloidal field coil and the first X point and between the geometric center position of the third poloidal field coil and the first X point are set to be 1-1.5a, 1.5-3a and 1.5-3a respectively, wherein a is the minor radius of a plasma. The method solves the technical problems that a divertor magnetic fieldconfiguration constructed by a conventional divertor magnetic field configuration construction method makes the target plate heating area small and target plate hot fluid faces huge challenges in a high heating condition. A hybrid divertor magnetic field configuration has capabilities of reducing inner and outer heat load of a divertor target plate and improving target plate particle control at the same time, and improves compatibility of running of a divertor and running of a core high heating plasma.