405 results about "Nuclear fusion" patented technology

The invention relates to the technical field of nuclear fusion devices, and discloses a nuclear fusion device and a monitoring system and an installation method thereof, the monitoring system comprises a cold shield main body, the cold shield main body is of an annular rotation structure, and the cold shield main body is arranged in a cavity and wraps the circumferential outer side of a vacuum chamber; the cold shield main body comprises a plurality of groups of fan-shaped cold shield sections which are sequentially arranged in the circumferential direction, and the plurality of groups of fan-shaped cold shield sections are encircled to form the cold shield main body; the distance measuring assembly is arranged on the cold shield main body, the distance measuring assembly comprises a plurality of groups of distance measuring sensors which are arranged in the circumferential direction of the cold shield main body at intervals, and each group of distance measuring sensors comprises a plurality of distance measuring sensors; the distance measuring sensor is used for detecting the size of a gap between the cold shield body and the longitudinal field coil and the size of a gap between the cold shield body and the vacuum chamber. Therefore, the cold shield main body can be assisted to be assembled at a position in the nuclear fusion device, and the matching position of the cold shield main body, the vacuum chamber and the longitudinal field coil can be monitored in real time.

The invention discloses a processing method of a fusion device, and belongs to the technical field of nuclear fusion. The processing method comprises the following steps: carrying out at least one time of vacuum heat treatment on a Dewar embedded part blank; carrying out cleaning anti-corrosion treatment and physical correction treatment on the surface of the dewar embedded part blank subjected to heat treatment; carrying out grinding and polishing treatment on the surface of the Dewar embedded part blank subjected to the cleaning and antiseptic treatment and the physical correction treatment to obtain the Dewar embedded part; the Dewar embedded part is transported to the installation position of the window to be installed, and the Dewar embedded part located at the installation position is temporarily fixed; performing concrete pouring on the mounting position of the Dewar embedded part; and after the concrete is solidified, a cast-in-place concrete structural body is formed in the area below the Dewar embedded part, and a part of the Dewar embedded part is embedded into the cast-in-place concrete structural body. By means of the method, the magnetic conductivity of the Dewar embedded part is reduced, and the risk that elements are activated to form isotopes with the long decay period and the high irradiation dose rate or isotopes with the short decay period and the high irradiation dose rate is reduced.

The invention relates to the technical field of nuclear fusion, and discloses a supporting device and a method for assembling a vacuum chamber and a cold shield of a nuclear fusion device.The supporting device comprises a first supporting assembly and a second supporting assembly, the first supporting assembly comprises a first clamping piece, a first supporting piece and a first adjusting piece, and the first clamping piece and the first supporting piece are spaced in the first direction and connected through the first adjusting piece; the first adjusting piece can adjust the distance between the first clamping piece and the first supporting piece in the first direction. The second supporting assembly comprises a second clamping piece, a second supporting piece and a second adjusting piece, the second clamping piece and the second supporting piece are spaced in the first direction and connected through the second adjusting piece, and the second adjusting piece can adjust the distance between the second clamping piece and the second supporting piece in the first direction; the third adjusting piece is connected with the first supporting piece and the second clamping piece and can adjust the distance between the first supporting piece and the second clamping piece in the first direction. The cold shield and the vacuum chamber can be clamped, and the gap between the cold shield and the vacuum chamber can be adjusted.

The invention provides a system and a method for off-line measurement of a cesium evaporation rate in a fusion device. The system comprises a vacuum chamber, a cesium crucible assembly, a heating assembly, a film thickness meter, a laser absorption spectrum system and a vacuum pumping unit. According to the invention, an ultrahigh vacuum environment is provided for the whole device including the vacuum chamber by using the vacuum pumping unit; then the cesium crucible and the conveying pipeline are heated through a heating assembly, so that effective evaporation of cesium is guaranteed, and deposition of cesium on the wall face of the pipeline is reduced; measuring the deposition thickness of cesium and the concentration of cesium atoms by using a film thickness meter and a laser absorption spectrum system, and checking the measurement results of the two diagnosis methods mutually; the cesium evaporation rate is measured, and the quantitative relation between the cesium evaporation rate and the heating temperature is obtained; and finally, a measurement system is transplanted into a negative ion source, and the cesium injection amount in the vacuum stage is monitored in real time. Effective data and technical support are provided for cesium flow control in the magnetic confinement nuclear fusion negative neutral beam injection system.

To provide a cold fusion device which offers a practical output level.SOLUTION: A capacitor consisting of a hydrogen-containing metal, which serves as a cold fusion target, and an opposing electrode is subjected to LC resonance, and the hydrogen-containing metal is irradiated with electrons with an energy level of 0.78 MeV or greater, generated in the capacitor, to promote nuclear fusion.SELECTED DRAWING: Figure 1

The invention relates to the field of nuclear fusion device installation, and discloses a supporting device of a nuclear fusion device preassembled assembly, and the supporting device of the nuclear fusion device preassembled assembly comprises a first supporting section, a second supporting section and an adjustable supporting section which are detachably connected in sequence along a first direction; the adjustable supporting section comprises a first adjusting part, a second adjusting part and a lifting part which are sequentially connected in the first direction, the first adjusting part is connected with the second supporting section and can drive the second adjusting part to be adjusted in the second direction, the second adjusting part can drive the lifting part to be adjusted in the third direction, and the lifting part can be adjusted in the first direction in a lifting mode. The first direction, the second direction and the third direction are perpendicular to one another. The supporting device of the preassembled assembly of the nuclear fusion device can support the bottom of the preassembled assembly, the position precision of the preassembled assembly can be improved, and the installation reliability of the nuclear fusion device is improved.

The invention provides a normal-temperature fusion target assembly, a laser fusion reactor system and a laser fusion power generation method.The fusion target assembly comprises a pair of coaxial compression cones with opposite cone tops, the compression cones are filled with normal-temperature boron deuteride lithium spherical crown targets, the fusion target assembly further comprises an ignition cone, and the cone tip end of the ignition cone is sleeved with a magnetic field coil; according to the light fusion power generation method, a spherical crown target is driven by compressed laser to generate centripetal implosion, high-density isometric plasma with a steep edge is formed near the sphere center in a collision mode, and tritium production reaction and fusion ignition combustion are generated by the collision plasma under driving of ignition laser. Energy released by high repetition frequency fusion is converted into electric energy which is stably output by a thermodynamic system; the invention further provides a laser nuclear fusion reactor system which is high in repetition frequency, low in cost and low in radioactivity.

Methods and systems are provided for increasing energy output from Z-pinch and other plasma confinement systems. In one example, a system may include memory storing instructions that, if executed by one or more processors, cause the system to adjust one or more parameters to generate a magnetic field which is sufficiently strong to axially compress a fuel gas to induce thermonuclear fusion and increase a fusion energy gain factor greater than a fusion energy gain factor limit attainable by the thermonuclear fusion. In certain examples, adjusting the one or more parameters may include adjusting a duty cycle of a discharge current applied to the fuel gas based, at least in part, on an amount of thermal collisions between fusion byproducts and the fuel gas. In certain examples, by adjusting the duty cycle, the magnetic field may be adjusted to induce or increase the thermal collisions.

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

The invention relates to the field of nuclear fusion devices, and discloses a fastening device and a mounting structure of a fusion reactor divertor system heat sink structure, and the fastening device of the fusion reactor divertor system heat sink structure is used for connecting the heat sink structure and a main body structure, and comprises a first connecting piece, a supporting disc, a second connecting piece, a first elastic piece and a third connecting piece, a first thread part is arranged on the outer side of the first connecting piece; the supporting disc is arranged in the first groove and is in clearance arrangement with the peripheral groove wall of the first groove; the second connecting piece penetrates through the second hole and is provided with a third groove; the first elastic piece is arranged in the second groove and elastically abuts against the skirt edge part. And the third connecting piece is arranged in the third groove and is in clearance arrangement with the peripheral groove wall of the third groove. A thermal expansion deformation space is reserved in the fastening device of the fusion reactor divertor system heat sink structure, damage to internal parts can be avoided, and the reliability of the fastening device of the fusion reactor divertor system heat sink structure is improved.

The invention relates to the technical field of nuclear fusion, and discloses a vacuum chamber cold shield module and a vacuum chamber cold shield for a nuclear fusion device.The vacuum chamber cold shield module comprises two panel assemblies and a cooling assembly, the two panel assemblies are arranged in the polar direction, and each panel assembly comprises an inner side panel assembly and an outer side panel assembly; the inner side panel and the outer side panel assembly surround a circle in the annular direction, the outer side panel assembly comprises a first outer side panel and a second outer side panel which are arranged in the polar direction, each panel assembly is correspondingly provided with two cooling assemblies, one cooling assembly surrounds the periphery of the first outer side panel and the periphery of the inner side panel in the annular direction, and the other cooling assembly surrounds the periphery of the second outer side panel in the polar direction. The other cooling assembly surrounds the periphery of the second outer side panel and the periphery of the inner side panel in the annular direction, each cooling assembly comprises a plurality of cooling pipelines, the cooling pipelines are arranged at intervals in the polar direction, and the cooling pipelines are filled with cooling media. The vacuum chamber cold shield module for the nuclear fusion device is convenient to mount, high in heat shielding efficiency and uniform in heat transfer performance.

The invention discloses a multi-mode magnetic field intelligent closed-loop plasma confinement system and method. The system comprises a multi-mode magnetic field generation module, a multi-dimensional plasma diagnosis module and a layered intelligent closed-loop control module. The multi-mode magnetic field generation module generates a steady-state, pulse and alternating composite magnetic field to realize adjustable space gradient; the multi-dimensional diagnosis module synchronously acquires electrical, optical and particle parameters, and ensures the accuracy through data fusion; and the hierarchical intelligent closed-loop control module generates an adjusting instruction to realize closed-loop optimization based on dynamic threshold and multi-algorithm scheduling. According to the method, the constraint performance is improved through the steps of initialization, data acquisition, state evaluation and closed-loop adjustment in combination with parameter self-optimization and three-level fault protection. According to the scheme, the plasma constraint time exceeds 300 s, the escape rate is lower than 5%, the adjustment response is smaller than or equal to 10 ms, the method adapts to multiple working conditions and can be popularized to the fields of nuclear fusion experiments and plasma processing, and the problems that a traditional system is poor in stability and lags in response are solved.

The invention provides an orthogonal electromagnetic field confinement fusion device and a fusion method. The fusion device comprises a vacuum combustion furnace which comprises a fusion reaction chamber and an inductance tube; the central shaft is arranged in the vacuum combustion furnace in a penetrating manner, a constant potential difference is applied between the inner wall of the vacuum combustion furnace and the central shaft, and a radial polarization electric field is generated in the vacuum combustion furnace; the inductance coil is wound on the outer wall of the vacuum combustion furnace, generates an axial confinement magnetic field in the vacuum combustion furnace and generates a magnetic mirror in the fusion reaction chamber; the fusion method comprises the following steps: S1, constructing an orthogonal electromagnetic field; s2, feeding fuel; s3, radially polarizing the ion ring; s4, induction of FRC is carried out; s5, axial fusion is carried out; s6, energy recovery; the device has the effects of simplifying the nuclear fusion reaction device, reducing the cost of the nuclear fusion reaction and improving the efficiency of the nuclear fusion reaction.

The invention provides an energy gradient utilization steam Rankine cycle power generation system and method for nuclear fusion, and belongs to the field of nuclear fusion energy conversion and utilization. Different temperature heat of a cladding, a divertor and a vacuum chamber is guided into a high-temperature independent heat storage loop, a medium-temperature independent heat storage loop and a low-temperature independent heat storage loop respectively, an operation section stores heat, and a pause section releases heat; feed water is heated step by step through a multi-stage preheater, an evaporator and a superheater according to the sequence of low temperature, medium temperature and high temperature, and superheated steam of 550 DEG C is formed to continuously drive a turbine to generate power. Decoupling of intermittent output of the fusion reactor and continuous operation of the power generation system is achieved, steam extraction of a steam turbine is omitted, the structure is simplified, and the energy utilization rate and the circulation efficiency are improved.

The present invention provides an appealing, fast, and cost-effective alternative to conventional nuclear fusion reactors. An ultra-compact spherical tokamak that combines three key features aimed at accelerating fusion energy as a viable energy source, these features are spherical type tokamaks, negative triangularity plasma shape and high-temperature superconducting coils. More specifically, the tokamak includes a toroidal vacuum vessel and a magnetic field system configured to confine a high temperature plasma. The magnetic field system includes a solenoid having a sand-hourglass shape; toroidal field coils having an inverse D-shaped design and high temperature superconductor (HTS) material; and poloidal field coils, external to the vacuum vessel. The vacuum vessel has a cross-section with similar inverse D-shape as the toroidal field coils.

The invention discloses a transfer device and a transfer method for transferring a polar field coil of a nuclear fusion device, and relates to the technical field of transfer of parts of the nuclear fusion device. The transfer device comprises a moving mechanism, a supporting mechanism, a supporting piece and a limiting piece, the supporting mechanism is fixedly arranged on the moving mechanism, and a supporting arm is formed on the supporting mechanism; the supporting pieces are in one-to-one correspondence with the supporting arms, each supporting piece is movably arranged in the extending direction of the corresponding supporting arm, and a clamping cavity used for containing at least part of the polar field coil is defined in each supporting piece; the limiting pieces correspond to the supporting arms one to one, each limiting piece is arranged on the corresponding supporting arm, the limiting pieces and the supporting pieces are connected through adjusting pieces, and the adjusting pieces are used for adjusting the distance between the supporting pieces and the limiting pieces. According to the transfer device, the transfer requirements of the polar field coil with large size, heavy weight and strict requirements can be met, it is guaranteed that the polar field coil is accurate in pose and reasonable in stress in the transfer process, and the requirements of the dynamic load coefficient and the unbalance load coefficient are met.

The invention provides a method and a device for inverting heat flow of a divertor based on a laser speckle image, and belongs to the technical field of nuclear fusion engineering thermal hydraulic testing. The device comprises a fusion reactor high heat flow simulation loading system, a laser speckle effect test system, a divertor water cooling simulation system and a test database system. A divertor target plate heat flow and loading surface strain corresponding database is established through the steps of adjusting cooling water flow conditions of a divertor test piece, carrying out series high heat flow loading on the divertor, measuring the divertor by adopting a laser speckle digital correlation technology and the like. In the actual reactor application, the surface strain of the same parts in the reactor is measured through the laser speckle technology, and the loaded heat flow inversion is realized through the corresponding query database. According to the method and the device for inverting the heat flow of the divertor based on the laser speckle image, quantitative inversion of the loaded heat flow of the divertor in an actual fusion reactor service environment is realized, and the operation safety of a nuclear fusion reaction device is improved.

All magnetic nuclear fusion devices face common technical challenges related to power and particle control arising from the close proximity of a thermonuclear plasma to the plasma-facing component. The plasma-facing component is subjected to high incident power density and erosion processes, and must facilitate the efficient remove of the fusion-ash. In the past, limiters and divertors have been used in magnetic fusion devices for this purpose. These are discussed and extended to a new concept, the “stochastic mantle”, which utilizes a stochastic magnetic field layer to disperse power on the plasma-facing component to the maximum extent possible. Further, if operated at sufficient plasma collisionality, it reduces the energy of particles incident on the plasma-facing component, globally reducing erosion by physical sputtering, while producing high gas pressures for fusion-ash removal through pumping ducts. The approach is particular suited for stellarators, but others devices may be considered.

The invention discloses a divertor structure of a Tokamak device and a design optimization method of the divertor structure, and relates to the technical field of magnetic confinement nuclear fusion. Based on a compact fusion reactor, the design of the physical structure of the divertor is carried out, and the physical structure of the divertor is optimized in combination with numerical simulation and evaluation technologies; according to the optimal divertor structure, the thermal load can be effectively controlled, and meanwhile the defects, limitation and the like caused by a configuration optimization technology and an external impurity injection technology are overcome; besides, in the design optimization process, the impurity injection effect, the impurity removal effect and the like are further considered, and therefore the optimal divertor structure further has the good impurity removal level and impurity shielding capacity.

The invention provides an attractive, fast and cost-effective alternative method for conventional nuclear fusion reactors. An ultra-compact spherical Tokamak which combines three key features intended to accelerate fusion energy as feasible energy sources, the features being a spherical Tokamak, a negative triangle plasma shape and a high temperature superconductor coil.

The invention discloses an assembling method and an assembling tool for a nuclear fusion device, and the method comprises the steps: S1, enabling a first sector and a first magnet to be sleeved outside a host hall, so as to form a standard sector, moving the standard sector to the host hall, and enabling the first magnet to rotate; sleeving of the second sector and the second magnet is completed in the host hall through the second sector and the second magnet; and S2, splicing the plurality of vacuum chamber sectors in the host hall in the circumferential direction, and splicing the plurality of magnetic field monomers in the circumferential direction. According to the assembling method of the nuclear fusion device, in the assembling process of the nuclear fusion device, the first sector and the first magnet are sleeved outside the main machine hall to form the standard sector, and the standard sector and the second sector and the second magnet are sleeved inside the main machine hall, so that the operation can be synchronously carried out, and the arrival time of the vacuum chamber sector and the magnetic field monomer can be reasonably utilized; the assembly efficiency of the nuclear fusion device is improved, and the assembly period is shortened.

The invention discloses a first wall structure for a nuclear fusion reactor, which comprises a tungsten armor, a front wall, a fin array and a rear wall which are sequentially connected through a diffusion welding process. A wing-shaped fin array is arranged between the front wall and the rear wall, a formed cavity serves as a coolant flow channel, and coolant enters the first wall through a set inlet and a set outlet. Due to disturbance of the fins, boundary layer separation and reattachment are generated between the adjacent fins, the heat exchange effect between the main flow and the boundary layer is remarkably enhanced, the heat exchange area is effectively increased, and therefore the heat exchange performance of the first wall is enhanced. The wing shape adopted by the invention is an excellent hydrodynamic appearance, and flow separation can be effectively reduced, so that the generation of separation vortexes can be greatly reduced, and the pressure loss of fluid can be effectively reduced.

The invention discloses a central column tool for general assembly of a nuclear fusion device host, and belongs to the technical field of nuclear fusion. The center column tool comprises a center column body which is installed in the center of a foundation pit and used for being connected with a center column embedded part located in the center of the foundation pit; the supporting parts are distributed in the circumferential direction of the center column body at intervals and used for being connected with wall embedded parts. The annular field sleeve annular rail is arranged around the central column body and is mounted on the supporting part; the supporting cross beams are distributed in the circumferential direction of the center column body at intervals, and the supporting cross beams are installed between the adjacent supporting parts; the non-standard fan-shaped section radial beams and the standard fan-shaped section radial beams are alternately distributed in the circumferential direction of the center column body at intervals, one ends of the non-standard fan-shaped section radial beams and the standard fan-shaped section radial beams are connected with the center column body, and the other ends of the non-standard fan-shaped section radial beams are connected with the supporting cross beams; and the circumferential field radial beam is rotatably mounted at the top end of the central column body. The general assembly of the main engine of the nuclear fusion device is carried out through the central column tool, and the general assembly efficiency can be remarkably improved.

The invention discloses a coil shielding structure for a linear magnetic confinement nuclear fusion device, and relates to the technical field of nuclear fusion reactors. Comprising a first shielding layer made of a metal material and capable of coating a coil conductor in an insulating manner; and the second shielding layer is made of a metal material and is coated outside the first shielding layer, and an outer cold flow channel is arranged between the second shielding layer and the first shielding layer. The multiple shielding layers are arranged in a laminated mode, electromagnetic wave conduction can be hindered by consuming electromagnetic energy for multiple times, eddy currents generated by a variable magnetic field on coil conductors (quasi-steady-state and cusped coils) are reduced, temperature rise of the coils is reduced, the current-carrying capacity of the coils is improved, the thickness of the shielding layers can be designed to be very thin, and the shielding layers are not prone to deformation. While the eddy current is reduced, the design cost of a conductor material and the self mass of a magnet system are reduced, and meanwhile, the second shielding layer can serve as a stress part to reinforce the mechanical structural strength of the magnet and prevent electromagnetic force from directly acting on a magnet coil to influence the established structure of the magnet coil.

Disclosed herein are methods, systems, media, and techniques for training machine learning models to generate nuclear fusion reactor configurations. Further disclosed herein are systems, methods, computer-readable media, and techniques for configuring a stellarator, including: (a) obtaining one or more parameters of a target stellarator; (b) generating a plurality of target stellarator approximations based at least in part on the one or more parameters of the target stellarator, wherein at least a subset of the plurality target stellarator approximations: (i) have a toroidal profile, and (ii) comprise a plurality of concentric toroids; and (c) presenting at a graphical user interface a representation of the plurality of target stellarator approximations.

The invention provides a multi-heat-source combined energy storage and auxiliary heating system and method for a nuclear fusion device, and belongs to the field of energy conversion and utilization of the nuclear fusion device, and the system comprises a high-temperature heat source storage and supply system which is used for receiving and storing heat of a cladding and a multiplication region coolant, and continuously outputting a high-temperature heat source during the operation and pause of a fusion reactor; the medium-temperature heat source and auxiliary supply system is used for receiving the heat of the divertor coolant and supplementing and outputting the medium-temperature heat source through a medium-temperature auxiliary heater during the suspension period of the fusion reactor; the low-temperature heat source and auxiliary supply system is used for receiving heat of the vacuum chamber coolant and supplementing and outputting a low-temperature heat source through a low-temperature auxiliary heater during the suspension period of the fusion reactor; the high-temperature heat source storage and supply system, the medium-temperature heat source and auxiliary supply system and the low-temperature heat source and auxiliary supply system operate independently. According to the invention, high-temperature heat, medium-temperature heat and low-temperature heat are simultaneously, continuously and stably supplied to the outside during operation and pause of the fusion reactor.

The invention relates to the field of controllable nuclear fusion devices, and discloses a magnetic shielding high-temperature lithium lead fluid pipeline section temperature field measurement system with temperature compensation, which comprises at least two groups of shielding pipes inserted into a test container, and the shielding pipes are arranged in parallel and located in the same plane. Temperature sensors are uniformly arranged on each shielding tube at intervals along the tube length direction; a magnetic field exists in the test container, the detection end of the temperature sensor penetrates through the shielding pipe body from the inside of the shielding pipe and then is in contact with a medium in the test container, and the pipe body of the shielding pipe is configured to shield the magnetic field in the test container. According to the invention, the real section temperature of the high-temperature lead-lithium alloy during flowing can be reflected, the measurement precision is improved, the influence of magnetoresistive effect or magnetothermoelectric force on data measured by the temperature sensor in a strong magnetic field environment is greatly reduced through temperature compensation, the measured data is close to actual data, the measured deviation value is relatively low, and the measurement accuracy is improved. The real section temperature of the high-temperature lead-lithium alloy during flowing can be reflected, and the measurement precision is improved.

A plasma generation system (10), and a nuclear fusion reaction system and method. The plasma generation system (10) comprises: a plasma generation assembly (101) and a motion assembly (102) connected to the plasma generation assembly (101), wherein the motion assembly (102) is configured to drive the plasma generation assembly (101) to move in a target direction; and the plasma generation assembly (101) is configured to emit plasma once same moves to a target position. The plasma generation system (10) can be used in a nuclear fusion reaction chamber (20) to generate a plasma ring therein, thereby reducing the difficulty in generating a plasma ring in the nuclear fusion reaction chamber (20), and thus improving the effect of a nuclear fusion reaction.

A renewable wall of a fusion reactor chamber is disclosed. In some embodiments of the disclosed technology, a fusion reactor device comprises a fusion reactor chamber including an inner wall that is at least partially made of a wall-forming aggregate to be exposed to a heat flux in the fusion reactor chamber during a nuclear fusion reaction which decomposes into constituent pebbles upon this heat flux exposure, a material collection system structured to collect via gravity, from the inner wall of the fusion reactor, a material recovery unit connected to the material collection system to recover the decomposed wall-forming material and provide a recovered wall-forming material to a wall-forming material container, and an array of extrusion channels connected between the inner wall and the wall-forming material container to feed the recovered wall-forming material from the wall-forming material container toward the inner wall of the fusion reactor chamber.

The invention discloses an equivalent shear force detection system for a nuclear fusion superconducting coil under a multi-element coupling working condition, and belongs to the field of conductor insulation development of the nuclear fusion superconducting coil. The system comprises a nuclear magnetic resonance scanner, a signal exchanger, a liquid helium cooling system, a superconducting coil immersed curing insulation composite material sample piece, a four-stage magnetic field, a bipolar magnetic field, a neutron irradiation probe, a liftable rotary mechanical arm and an AI large model processing server. Completing the detection of the equivalent shearing force of the superconducting coil insulating material under the working conditions of magnetic coupling, neutron irradiation and the like in the nuclear fusion reaction stage; the insulation material equivalent shear force detection system can detect the endogenous organization structure change of the insulation composite material of the superconducting coil in the nuclear fusion reaction stage, and can avoid the situation that the electric insulation composite material of the superconducting coil is forced to be interrupted in the nuclear fusion reaction due to fatigue damage caused by concentrated equivalent shear force.