62 results about "Divertor" patented technology

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 present disclosure provides methods and divertors for plasma reactors. The divertors may comprise internal lattice structures to facilitate conductive and convective heat transfer and provide structural support to plasma facing surfaces of the divertor.

The application discloses a surface thermocouple system suitable for a full-tungsten divertor of a magnetic confinement device, and relates to the field of plasma diagnosis of magnetic confinement devices, and comprises a box-shaped support structure and a thermocouple assembly. The tungsten-copper string tube of the divertor is fixedly connected with the box-shaped support structure through fixing pins. The thermocouple assembly is composed of a thermocouple probe, a pyrolytic graphite shell, a base, a screw, a nut, a spring washer, a fixing support plate and a lead wire, and is installed in a cylindrical through hole between adjacent tungsten-copper string tubes and a gap between the tungsten-copper string tube and the box-shaped support structure. The application enables the surface thermocouple to be normally disassembled and maintained, and provides a direct means for measuring the surface temperature of the target plate of the full-tungsten divertor.

The application provides a multi-heat source combined energy storage and auxiliary heating system and method of a nuclear fusion device, and belongs to the field of nuclear fusion device energy conversion and utilization, and comprises: a high-temperature heat source storage and supply system, which is used for receiving and storing the heat of blanket and breeding zone coolants, and continuously outputs high-temperature heat sources during the operation and suspension of a fusion reactor; a medium-temperature heat source and auxiliary supply system, which is used for receiving the heat of a divertor coolant, and supplements the output of medium-temperature heat sources through a medium-temperature auxiliary heater during the suspension of the fusion reactor; and a low-temperature heat source and auxiliary supply system, which is used for receiving the heat of a vacuum chamber coolant, and supplements the output of low-temperature heat sources through a low-temperature auxiliary heater during the suspension of the fusion reactor; and 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 are independently operated. The application continuously and stably provides high-temperature heat, medium-temperature heat and low-temperature heat to the outside during the operation and suspension of the fusion reactor.

The present application belongs to the field of fusion reactor filter target plate cooling, and particularly relates to a filter target plate with composite micro-channel and super-vaporization structure cooling. The filter target plate comprises a plasma-facing material layer, a stress buffer layer, a micro-channel and super-vaporization composite structure heat sink, and a stainless steel cover plate. The micro-channel cooling is used in the micro-channel and super-vaporization composite structure heat sink corresponding to the strike point area of the target plate, and the super-vaporization channel cooling is used in the micro-channel and super-vaporization composite structure heat sink corresponding to the remaining area of the target plate. The present application can significantly reduce the surface temperature of the plasma-facing material in the strike point area of the target plate, prolong the service life of the filter target plate, and more efficiently transfer the ultra-high heat load deposited in the strike point area of the filter target plate, so as to ensure that the temperature of the plasma-facing material is lower than the recrystallization temperature of the material.

The application relates to the technical field of fusion reactors, and discloses an assembly tool and an assembly method for a divertor. The box body is positioned and installed to the assembly tool through a first positioning surface, a second positioning surface and a third positioning surface; the first reference surface and the second reference surface are used to set a reference coordinate system when the assembly and the detection of the target plate are performed, and the target plate is detected and adjusted by taking the reference coordinate system as a reference, so that the profile tolerance of the target plate meets the error allowable range, and then the assembly precision of the divertor obtained through the assembly tool is guaranteed; the box body is installed to the assembly tool through the assembly tool, the target plate is preliminarily positioned and matched with the box body, a laser tracker is used to establish the reference coordinate system and acquire the actual profile of the target surface of the target plate, and the target plate is adjusted correspondingly, so that the assembly precision is improved, and the normal work of the divertor is effectively guaranteed; and the leakage test is used to guarantee that the cooling channel can normally perform the cooling work.

The invention relates to the technical field of nuclear fusion reactor energy conversion, in particular to a conduction oil heat storage preheating system suitable for an intermittent operation fusion reactor and a working method. The heat conduction oil heat storage preheating system comprises a fusion reactor divertor heat removal system, a fusion reactor vacuum chamber heat removal system and a heat conduction oil heat storage system. The conduction oil heat storage system comprises a first heat storage heat exchanger, a second heat storage heat exchanger, a preheating heat exchanger, a high-temperature oil tank, a low-temperature oil tank, a low-temperature oil pump and a high-temperature oil pump. An outlet of the low-temperature oil tank is connected to an inlet of the low-temperature oil pump, an outlet of the low-temperature oil pump is connected to an inlet of the second heat storage heat exchanger, and an outlet of the second heat storage heat exchanger is connected to an inlet of the first heat storage heat exchanger. Through reasonable configuration of the fusion reactor energy conversion system, the contradiction between the pulse operation mode and the continuous stable power generation requirement can be effectively relieved, and it is ensured that the working medium flow, temperature and power are stable and controllable in the preheating process.

The invention relates to the field of field antiform fusion, particularly provides a target plate fault processing method and device based on a divertor, equipment and a medium, and aims to solve the technical problem that a field antiform fusion device cannot operate stably due to the fact that the fault of a target plate cannot be found and solved in time in the prior art. In order to achieve the purpose, the method comprises the steps of obtaining target plate state data of a to-be-detected target plate; the target plate state data comprises surface element distribution, target plate internal data, a surface temperature field and mechanical vibration acceleration; preprocessing the target plate state data of the to-be-detected target plate to obtain preprocessed data of the to-be-detected target plate; inputting the preprocessed data of the to-be-detected target plate into a target plate classification model to obtain target plate classification; and processing the field antiform fusion device according to the classification of the target plates.

The present application relates to the technical field of fusion device, and more particularly to a heat and mass transfer experiment platform of a gas baking system of a divertor. The technical scheme comprises a gas baking system, a vacuum system, a secondary side cooling system and a data acquisition and control system. The gas baking system comprises a Roots blower, the Roots blower is connected with a regenerator, the regenerator is connected with an electric heater and a cooler respectively; the vacuum system comprises a vacuum tank and a vacuum assembly installed on the vacuum tank, and the electric heater is connected with an experimental piece inside the vacuum tank. The present application can establish a heat and mass transfer model, help to understand the heat and mass transfer law, optimize the design and operation of the device, reveal the influence mechanism of the baking temperature, the working medium pressure and the flow rate, ensure the baking safety and stability, test the influence of different gas working media on the baking characteristics, test the vacuum leakage characteristics, find and solve problems in time, and ensure the high vacuum environment, reliability and stability of the fusion device.

The invention belongs to the field of nuclear fusion device application, and discloses an inlet and outlet coaxial cooling structure of a fusion device divertor heat sink structure. The cooling structure comprises an outer flow channel component and an inner flow channel component which are coaxially arranged, the outer flow channel component and the inner flow channel component are arranged at the edge position of the heat sink structure and can be horizontally and axially mounted in the heat sink structure and the main body structure which are arranged at an interval in a floating manner; an inner flow channel is arranged in the inner flow channel part, and the inner flow channel is communicated between an outlet of a cooling flow channel in the heat sink structure and an inlet of a liquid outlet flow channel in the main body structure; an outer flow channel is formed in the outer flow channel component and between the outer flow channel component and the inner flow channel component; and the outer flow channel is communicated between an inlet of the cooling flow channel and an outlet of a liquid inlet flow channel in the main body structure. The reasonable temperature gradient of the whole heat sink structure is achieved, it is guaranteed that the strength of the main body structure is reliable, the whole structure is compact, complex connection of external pipelines can be reduced, installation and maintenance are convenient, and the maintenance cost is low.

A method of repairing a divertor or first wall surface in a tokamak plasma vessel. The divertor or first wall surface comprises a refractory metal having a melting point of at least 2000° C. A pressure of less than 25 mbar is maintained within the plasma vessel following the end of operation of the plasma vessel. The refractory metal is deposited onto the divertor or first wall surface within the plasma vessel via a deposition process which is one of: additive manufacturing; physical vapour deposition; thermal spray; arc ion plating; diode laser cladding; and chemical vapour deposition.

The invention provides an energy conversion system suitable for a pulse operation fusion reactor and an operation method thereof, relates to the technical field of fusion reactor control, and solves the problems of high investment and operation cost of an intermediate heat storage loop scheme, fatigue operation and carbon emission of equipment in a boiler energy compensation scheme and the like. In the system, a cladding primary loop, a vacuum chamber primary loop and a divertor primary loop respectively load heat energy to a secondary loop; the secondary loop is provided with a steam turbine for converting steam heat energy of the steam generator into mechanical energy and outputting the mechanical energy to the power generation system to generate electric energy; the heat storage and release system is connected into a first cladding loop through two heat exchangers, and the heat storage process and the heat release process are achieved respectively. And the heat storage and release system is based on the low-temperature heat storage tank and the high-temperature heat storage tank, so that the fused salt medium is recycled in a pipeline of the heat storage and release system. On the premise of ensuring efficient power generation and radioactive safety, the system has the advantages of low investment and operation cost, high flexibility and the like, and is suitable for energy conversion of fusion demonstration reactors and commercial reactors.

The application relates to the technical field of fusion reactors and discloses a double-V-shaped closed divertor compatible with multiple elongation ratios, which comprises an inner divertor used for reflecting plasma, sending recycled particles and impurity particles formed by reflection into an outer divertor, a first outer divertor comprising a first particle reflection baffle and a second particle reflection baffle, the first particle reflection baffle and the second particle reflection baffle forming a V-shaped closed structure, and the first particle reflection baffle and the second particle reflection baffle both being used for reflecting the recycled particles and the impurity particles to a strike point direction. The application can effectively close the recycled particles and the impurity particles near a strike point of a divertor target plate, so that a large amount of recycled neutral particles and impurity particles reflected to the strike point are instantaneously ionized, thereby rapidly radiating energy, greatly reducing heat flow deposited to the V-shaped closed divertor, and effectively solving the high heat load problem of an HL-3 device.

A high performance field reversed configuration (FRC) system includes a central confinement chamber, two divertor chambers coupled to the chamber, and two diametrically opposed spheromak injectors coupled to the divertor chambers. A magnetic system includes quasi-de coils axially positioned along the FRC system components.

The application relates to a pressureless preparation method of a capillary pore structure based on tungsten-based medium-entropy material applied to a filter, and belongs to the technical field of fusion reactor filters. A three-dimensional model is constructed according to the capillary pore structure; W, Cu, Cr and V four kinds of metal powders are added into a first ball mill jar, Cu and Cr two kinds of metal powders are added into a second ball mill jar, the two ball mill jars are mixed after ball milling, and tungsten-based medium-entropy alloy powder is obtained; paraffin and stearic acid are fully mixed, and then heated to a molten state to obtain a paraffin-based bonding agent; the medium-entropy alloy powder is preheated and added into the paraffin-based bonding agent to obtain a metal slurry; the paraffin pre-prepared framework is preheated, the metal slurry is injected, a hot-pressing die is used, and a tungsten-based medium-entropy alloy pore structure blank is obtained after cooling; and then, degreasing and sintering are carried out, so that the capillary pore structure based on the tungsten-based medium-entropy material is obtained. The capillary pore structure prepared by the pressureless preparation method has better structural bearing capacity and impact resistance.

A tokamak plasma vessel. The tokamak plasma vessel comprises a toroidal plasma chamber, a plurality of poloidal field coils, an upper divertor assembly, and a lower divertor assembly. The plurality of poloidal field coils are configured to provide a poloidal magnetic field having a substantially symmetric plasma core and an upper and lower null, such that ions in a scrape off layer outside the plasma core are directed by the magnetic field past one of the upper and lower nulls to divertor surfaces of the respective upper and lower divertor assembly. Each of the upper and lower divertor assembly comprises a liquid metal inlet and a liquid metal outlet located below the liquid metal inlet. Each of the upper and lower divertor assembly is configured such that in use liquid metal flows from the liquid metal inlet to the liquid metal outlet over at least one divertor surface of the divertor assembly.

A divertor assembly for use in a magnetic confinement plasma chamber. The divertor assembly comprises a divertor plate, a gas source, and a system. The divertor plate has an external plasma facing surface and one or more conduits extending through the divertor plate to open at the external plasma facing surface. The gas source is configured to provide a gas to the conduits. The system is configured to control the flow of gas from the gas source to the external plasma facing surface.

The invention belongs to the cross technical field of a nuclear fusion energy technology and a heat-work conversion system, and provides a nuclear fusion Rankine cycle structure integrating divertor heat recovery, which comprises a primary side heat collection module and a secondary side heat-work conversion module, the heat-power conversion module comprises a steam generator, a first valve, a high-pressure turbine, a dehumidifier, a reheater, a low-pressure turbine, a condenser, a first water pump, a first feed water heater, a second feed water heater, a deaerator, a second water pump, a third feed water heater and a preheating heat exchanger which are sequentially connected through pipelines; the preheating heat exchanger preheats secondary side supplied water before entering the steam generator through heat of the divertor. And the outlet water temperature of the third feed water heater is matched with the temperature of the preheating heat exchanger by adjusting the inlet steam extraction flow of the third feed water heater. According to the structure, gradient utilization of nuclear fusion heat is achieved, and irreversible loss in the heat exchange process is reduced.

The application relates to the field of nuclear fusion devices, and discloses a fastening device and mounting structure of a fusion reactor filter system heat sink structure, which is used for connecting a 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, the first connecting piece is circular and is provided with a first threaded portion on the outer side; the supporting disc is arranged in a first groove and is arranged in a gap with the circumferential groove wall of the first groove; the second connecting piece is arranged through a second hole and is provided with a third groove; the first elastic piece is arranged in the second groove and is elastically abutted against a skirt portion; and the third connecting piece is arranged in the third groove and is arranged in a gap with the circumferential groove wall of the third groove. The fastening device of the fusion reactor filter system heat sink structure has a thermal expansion deformation space inside, can avoid damage of internal components, and improves the reliability of the fastening device of the fusion reactor filter system heat sink structure.

The invention provides a particle discharging device and method for a Tokamak divertor area. The device comprises an adsorbent pump unit arranged in a divertor area and a gas channel structure communicated with the divertor area, and is used for capturing and discharging neutral particles generated by interaction of plasma and divertor components. The adsorbent pump unit is made of a non-evaporation type adsorbent material, has high adsorption capacity on hydrogen and isotopes thereof, can keep stable structure and working performance under the condition of high temperature, and is suitable for a high-heat-load and high-particle-flux operating environment in a divertor area. The in-situ air exhaust of the neutral particles is realized in the divertor area, so that the transport path of the particles is shortened, and the response speed and efficiency of particle discharge are improved. Meanwhile, the particle discharging device has large air extraction capacity and effective extraction speed, is suitable for tritium-related application scenes and operating environments with neutron irradiation, and has good engineering application prospects.

The application relates to the technical field of nuclear fusion devices, and discloses a manufacturing method of a divertor box body of a nuclear fusion device, which is manufactured based on an assembly tool, the assembly tool comprises a body part with a first part and a second part oppositely arranged in the length direction of the divertor box body, and the manufacturing method comprises the following steps: manufacturing the divertor box body in sections so that the divertor box body is formed into at least two separate first and second modules; machining a bevel on the bottom plate of each of the first and second modules, and oppositely arranging the bevels to form a welding groove; arranging the first module on the first part and the second module on the second part, the top surface profiles of the first and second parts being respectively matched with the bottom surface profiles of the first and second modules and being tightly combined; and welding the divertor box body at the welding groove. The manufacturing efficiency of the divertor box body is improved, the manufacturing cost of the divertor box body is reduced, and the manufacturing quality of the divertor box body is ensured.

A double null, DN, plasma control system for a magnetic confinement apparatus. The DN plasma control system comprises a first poloidal field coil configured to be positioned proximate to a first divertor of the magnetic confinement apparatus and a magnetic flux monitoring system configured to obtain magnetic flux values of a first X-point and a second X-point of a magnetic field generated by the magnetic confinement apparatus. The DN plasma control system further comprises a control system configured to receive the obtained magnetic flux values of the first X-point and the second X-point, and to control a difference in magnetic flux between the first X-point and the second X-point using the first poloidal field coil.

The application provides an energy cascade utilization steam Rankine cycle power generation system and method for nuclear fusion, belonging to the field of nuclear fusion energy conversion and utilization. Different temperature heat of a cladding, a divertor and a vacuum chamber is introduced into high, medium and low temperature independent heat storage circuits respectively, heat storage is performed in a running section and heat release is performed in a pause section; feed water is sequentially heated by a multistage preheater, an evaporator and a superheater in sequence to form 550 DEG C superheated steam to continuously drive a steam turbine to generate power. The application realizes decoupling of intermittent output of a fusion reactor and continuous operation of a power generation system, cancels steam extraction of the steam turbine, simplifies the structure and improves energy utilization rate and cycle efficiency.

The invention discloses a surface thermocouple system suitable for an active water-cooling all-tungsten divertor of a magnetic confinement device, which relates to the field of plasma diagnosis of the magnetic confinement device and comprises a box-shaped supporting structure and a thermocouple assembly. Tungsten copper string pipes of the divertor are fixedly connected with the box-shaped supporting structure through fixing pins, and the thermocouple assembly is composed of a thermocouple probe, a pyrolytic graphite shell, a base, a screw, a nut, a spring washer, a fixing supporting plate and a lead and installed in cylindrical through holes between the adjacent tungsten copper string pipes and gaps between the tungsten copper string pipes and the box-shaped supporting structure. According to the invention, the surface thermocouple can be normally disassembled and maintained, and a direct means is provided for measuring the surface temperature of the active water-cooled all-tungsten divertor target plate.

The application discloses a fusion reactor filter facing plasma component structure and a preparation method thereof. The inner target plate transition and the dome transition support are integrated and designed. The inner target plate (dome) transition support and the outer target plate transition support are respectively prepared by using two kinds of materials. The internal S-shaped flow channel and the current collecting box are used for flow channel connection. In the inner and outer target plate V-shaped area, the plasma facing unit is connected with the current collecting box in the transition support through the elbow pipe. The intermediate flow channel in the transition block is used for connecting the coolants flowing through the horizontal and vertical target plates. The preparation process of the plasma facing component includes the plasma facing unit manufacturing, the vertical and horizontal target plate transition support and transition block processing, the transition block main body and the vertical and horizontal target plate welding, the transition block lower end cover welding, the S-shaped cover plate and the horizontal lower cover plate welding, and local finishing, and the structure and the preparation method have the advantages of high heat load bearing, uniform fluid distribution, and feasible processing.

The invention discloses a method for observing spatial distribution characteristics of deuterium and impurities of a lower divertor by using hyperspectral imaging, which comprises the following steps of: when a magnetic confinement fusion device runs, realizing multiband 2D image observation of a lower divertor region through a hyperspectral camera, and realizing continuous recording of emission spectral lines of deuterium and impurity elements of the lower divertor; arranging the obtained multiband spectral intensity data in the 2D space, establishing a corresponding database according to corresponding shot numbers, and carrying out calibration analysis on spectral information intensity recorded by a camera through an integrating sphere standard light source to obtain absolute intensity data of emission spectral lines in the multiband; and determining corresponding element information by combining the special emission spectral line wavelengths of different elements recorded in the ADAS atom database. Multiband spectral information data recorded by hyperspectral imaging can provide a basis for research on spatial 2D profile distribution of boundary plasma parameters and tungsten impurity spectral lines, and provide data support for evaluation of first wall tungsten impurity source distribution and tungsten impurity sputtering conditions.

The invention provides a fusion reactor divertor heat sink tungsten dispersion copper module functionally graded material connection method, and relates to the field of nuclear fusion device application, the fusion reactor divertor heat sink tungsten dispersion copper module functionally graded material connection method comprises the following steps: carrying out micro-nano etching on a to-be-connected surface of a tungsten sheet to form a groove array with a depth-to-width ratio of 5: 1, the groove depth being 100-200 [mu] m, and the spacing being 50-100 [mu] m; the preparation method comprises the following steps: preparing a W / ODS-Cu functionally graded material intermediate layer, sequentially transitioning components from pure tungsten to at least two W / ODS-Cu layers and then to pure ODS-Cu through spark sintering, so that the content of the ODS-Cu is progressively increased from 0 vol% to 100 vol%, the total layer thickness is 0.5-0.8 mm, and 0.5-2 wt.% of Y2O3 and 1-3 wt.% of TiC composite particles are doped in each layer; and the etched tungsten sheet, the W / ODS-Cu functional gradient material middle layer and the ODS-Cu structural part are assembled and then subjected to vacuum hot isostatic pressing treatment. According to the invention, an integrated process is realized.

The invention discloses a device and a method for diagnosing the surface topography of a divertor of a Tokamak device, and relates to the field of EAST Tokamak devices. Comprising a light source module, an optical fiber coupling system and a holographic imaging system. According to the invention, a novel detection structure is adopted, and a common-path scheme is utilized to construct a divertor surface topography measurement system; a single-mode optical fiber is adopted to carry out optical path distribution on a coherent light source, and a receiving and transmitting common path mode is adopted to overcome the actual constraint of Tokamak so as to meet the measurement condition of a divertor; through a spectrum multiplexing technology, a dual-wavelength hologram can be recorded in single shooting, and single acquisition imaging is realized, so that a measurement system is simplified, instantaneous acquisition is realized, the detection pressure of the device is reduced, the detection range is expanded, and the influence of vibration on the detection precision in divertor morphology detection is effectively solved.

The invention discloses a slice type manifold divertor cooling structure and a manufacturing method thereof, and belongs to the technical field of nuclear fusion devices. The cooling layer comprises a plurality of high-temperature, high-strength and high-conductivity copper sheet slices which are stacked, and the stacking sequence is a first side baffle slice, a first conventional flow channel slice, a baffle slice only containing a micro-channel, a second conventional flow channel slice and a second side baffle slice; micro-channel structures are cut at the tops of the first conventional flow channel slice and the second conventional flow channel slice, and conventional flow channels are arranged below the micro-channel structures; a micro-channel structure is arranged at the top of the baffle slice only containing the micro-channel, and a water inlet pipe and a water outlet pipe are arranged at the two ends of the baffle slice only containing the micro-channel respectively. According to the divertor, a manifold micro-channel cooling technology is introduced into the divertor, so that the contact area between cooling fluid and a heat sink is increased, the heat transfer efficiency in unit time is improved, and the thermal load capacity of the divertor is remarkably improved.