128 results about "Divertor" patented technology

The invention belongs to the technical field of magnetic confinement controllable thermonuclear fusion, and particularly relates to an in-situ laser diagnosis system and method for plasma fuel thermal desorption / impurity deposition in a wall material. The long-pulse laser module emits a long-pulse laser beam, and the long-pulse laser beam sequentially passes through the dichroscope I, the convex lens, the dichroscope II and quartz glass on the vacuum chamber and is irradiated to the surface of the sample to be detected; the short-pulse laser module emits a short-pulse laser beam, and the short-pulse laser beam sequentially passes through the dichroscope I, the convex lens, the dichroscope II and quartz glass on the vacuum chamber of the fusion device and is irradiated to the surface of the sample to be detected; the irradiated radiation light of the to-be-detected sample sequentially passes through the focusing lens, and a spectral signal is transmitted to the spectrum acquisition system. According to the system, high-efficiency in-situ laser thermal desorption can be carried out on fuel gas retained in a wall material, in-situ laser diagnosis of impurity deposition can also be carried out, the two methods are flexibly coupled into one set of system and can be independently used or simultaneously carried out, and a reference basis is provided for fusion reactor divertor operation control and wall material research and development in the future.

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.

An annular confinement plasma vessel having a substantially symmetric magnetically confinement plasma region wherein the plurality of magnetic field coils are configured to provide at least one X-point and direct plasma particles from the magnetically confinement region to the divertor target; and wherein the total magnetic field strength (including all components of the magnetic field) at the divertor target is lower than the total magnetic field strength (including all components of the magnetic field) at a location between the divertor target and the X point on the last closed flux surface of the SOL closest to the divertor target. When the mean free path of the neurons is longer than the width of the SOL, the two critical functions can be separated: a) withstanding high heat flux, and b) pumping plasma particles to maintain low density.

The invention discloses a design method of a star simulator three-dimensional divertor target plate, and belongs to the technical field of magnetic confinement fusion. The method comprises the following steps: firstly, deducing a circumferential thermal load uniformity theoretical model, then, calculating background information required by target plate generation, and finally, carrying out target plate generation by using the obtained background information and the circumferential thermal load uniformity theoretical model. The target plate is generated based on parameter control, the target plate capable of achieving uniform distribution of the circumferential thermal load is provided, the circumferential uniform distribution of the thermal load of the divertor target plate can be effectively improved, and the peak value of the thermal load of the divertor target plate can be effectively reduced. The target plate generated by the method conforms to standard output formats among different analog calculations. Data can be conveniently transmitted between integrated simulation platforms, and the working process is simplified. The divertor target plate is generated on the basis of the basic physical assumption that the magnetic lines of the magnetic field and the heat flow are attenuated along the radial position, and the method is suitable for all star simulator devices with three-dimensional magnetic island structures and has universal applicability.

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 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.

The invention discloses a divertor target plate thermal load and impurity control combined gas injection method and system, and the method comprises the steps: arranging two gas injection ports in a divertor, and respectively injecting impurities argon and deuterium gas through the two gas injection ports. The combined gas injection method is adopted, the thermal load peak value of the divertor target plate can be effectively controlled to be lower than 10 MWm <-2 >, in other words, the thermal load peak value of the divertor target plate is effectively controlled to be lower than the engineering limit, and therefore it is ensured that the divertor can stably run for a long time; besides, compared with existing impurity control which is easy to introduce new impurities and cannot realize effective control of the impurities, a combined gas injection mode is adopted, the peak value of the effective charge quantity at the edge and the particle density of the impurity at the edge can be effectively controlled, and the impurity at the edge is controlled at a lower level; and adverse effects caused by impurity injection in the prior art are greatly reduced.

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 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 technical field of fusion reactors, and discloses an assembly tool and an assembly method of a divertor, a box body is positioned and mounted on the assembly tool through a first positioning surface, a second positioning surface and a third positioning surface; through the first reference surface and the second reference surface, a reference coordinate system is set during assembly and detection of the target plate, 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 conforms to an error allowable range; therefore, it is guaranteed that the divertor obtained through assembling of the assembling tool has enough assembling precision; by the adoption of the assembling tool, the box body is installed on the assembling tool, then the target plate and the box body are preliminarily positioned, a reference coordinate system is established in cooperation with a laser tracker, the actual contour of the target surface of the target plate is obtained, the target plate is correspondingly adjusted, the assembling precision is improved, and normal work of a divertor is effectively guaranteed; and the normal cooling work of the cooling channel can be ensured through the leak detection test.

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 invention discloses an energy comprehensive utilization system based on a fusion device and a control method thereof. The system comprises a divertor cooling circulation loop, a cladding tritium production loop, a first cooling loop, a second cooling loop, a Brayton circulation loop and a Rankine circulation loop. The first cooling loop and the second cooling loop are used for cooling and purifying the cladding, and when the thermal load of the fusion device is smaller than a preset threshold value, only the first cooling loop is operated; when the thermal load of the fusion device is larger than a preset threshold value, the first cooling loop and the second cooling loop operate in parallel. The second cooling loop is indirectly or directly connected with the Brayton cycle loop or the Rankine cycle loop through valve switching; the Brayton cycle loop and the Rankine cycle loop are power generation loops, and power generation modes comprise Rankine cycle power generation, Brayton cycle power generation and combined power generation of Rankine cycle and Brayton cycle. The energy comprehensive utilization of the fusion device can be realized, and meanwhile, the system flexibility is improved.

The invention relates to the technical field of fusion energy heat feedback systems, in particular to a loop structure of a fusion energy heat feedback system. According to the technical scheme, the device comprises a cladding cooling loop and a divertor cooling loop; the cladding cooling loop comprises a cladding, a main circulating pump I, a steam generator, a heater and a voltage stabilizer I which are connected in sequence to form a loop; the first main circulating pump is connected with a first baking small-flow pump in parallel, the steam generator is connected with a first flow adjusting valve and a first baking cooler in parallel, and the heater is connected with a second flow adjusting valve in parallel. The divertor cooling loop comprises a divertor, a second main circulating pump, a main heat exchanger, a second baking small-flow pump and a second voltage stabilizer which are sequentially connected to form the loop. The problem of high-temperature baking of internal parts of the fusion reactor is effectively solved, fusion energy is safely, stably and efficiently output for power generation, energy shortage and environmental pollution are relieved, the practical process of nuclear fusion energy is accelerated, and the system has multiple safety guarantee mechanisms.

The present disclosure may provide methods and systems for exhausting particles from a plasma field using, at least in part, the backside surface of a divertor.

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-dc coils axially positioned along the FRC system components.

The present disclosure may provide methods and systems for exhausting particles from a plasma field using, at least in part, the backside surface of a divertor.

The application discloses a kind of energy comprehensive utilization system based on fusion device and its control method, the system includes: divertor cooling circulation loop, blanket tritium production loop, first cooling circuit, second cooling circuit, brayton cycle loop and rankine cycle loop;First cooling circuit and second cooling circuit are used for blanket cooling and purification, when the heat load of fusion device is less than preset threshold, only first cooling circuit is operated;When the heat load of fusion device is greater than preset threshold, first cooling circuit and the second cooling circuit are operated in parallel;Second cooling circuit is indirectly connected or directly connected with brayton cycle loop or rankine cycle loop by valve switching;Brayton cycle loop, rankine cycle loop is power generation circuit, and power generation mode includes rankine cycle power generation, brayton cycle power generation, combined power generation of rankine cycle and brayton cycle.The application can realize fusion device energy comprehensive utilization, and improve system flexibility simultaneously.

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.

A method of repairing a divertor or first wall surface in a tokamak. The tokamak comprises a vacuum chamber having a port; a vacuum maintenance system configured to maintain a pressure of less than 25 mbar within the vacuum chamber; a first wall and a divertor, each having a surface comprising a refractory metal having a melting point above 2000°C. The vacuum maintenance system maintains a pressure of less than 25 mbar within the vacuum chamber following suspension of operation of the tokamak. The refractory metal is deposited onto the divertor or first wall surface via a deposition process comprising providing one or more reagents to the chamber in gaseous or plasma form via the port, the reagents being capable of reacting chemically to form the refractory metal and a gaseous by-product; and heating the divertor or first wall surface to a temperature sufficient to cause the reagents provided to the chamber to react therein to form the refractory metal and the gaseous by-product. The vacuum maintenance system removes the gaseous by-product and any excess reagent from the chamber after deposition of the refractory metal.

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 belongs to the technical field of nuclear fusion device application, and discloses a fusion device divertor strain / temperature monitoring system, which is characterized in that an optical fiber capillary packaging part is fixedly arranged on a divertor box body from the high field side of the divertor box body along the appearance direction of the divertor box body, and is led out from the low field side of the divertor box body to be connected to a demodulator; the strain fiber grating sensors are distributed along the optical fiber capillary packaging part and are pre-tightened and fixed at strain monitoring points of the divertor box body; the temperature fiber grating sensors are distributed along the optical fiber capillary packaging part and are located at the temperature monitoring point positions of the divertor box body; no strain fiber grating sensor is arranged on the fiber capillary packaging piece provided with the temperature fiber grating sensor. The device is suitable for multi-point dense arrangement on the divertor box body, the strain / temperature of the divertor box body can be comprehensively monitored in real time, and monitoring data are reliable and effective.

The invention discloses a divertor target plate small-angle thermal load simulation device and detection method.The device comprises a discharge unit and an inflation unit arranged at one end of the discharge unit, the discharge unit comprises an insulation block, one end of the insulation block is provided with a first end cover, and the other end of the insulation block is provided with a second end cover; the first end cover, the insulating block and the second end cover are provided with first through holes along the axis, the first through holes are used for installing a copper-tungsten electrode, a first capillary tube, a second capillary tube, a first main electrode and a second main electrode which are connected in sequence, the first capillary tube comprises a first capillary tube accessory and a second capillary tube accessory, and a target groove is formed in the second capillary tube accessory and used for installing a tungsten target; the arrangement of the first gap, the second gap, the third gap and the fourth gap is used for preventing external gas or internal helium plasma from leaking from each connecting part, voltage is applied to the first end cover and the second end cover to break down the gas in the discharge channel, and helium plasma jet is formed under the pushing of pressure and the gas to impact the tungsten target at a small angle.

The application belongs to the technical field of magnetic confinement nuclear fusion devices, and discloses a liquid lithium divertor device. The liquid lithium divertor device comprises a liquid film generator, the liquid film generator comprises a liquid lithium input area and a liquid lithium conveying area; a divertor target plate and a heating bottom plate are detachably connected to the liquid lithium conveying area; the inlet of the liquid lithium input area is in communication with a conveying pipeline, a plurality of first sub-flow channels are arranged in a dendritic structure in the liquid lithium input area; the inlet of the liquid lithium conveying area is in communication with the outlet of the first sub-flow channel through a vertical flow channel, the outlet of the liquid lithium conveying area is in contact with the top of the divertor target plate, and the flow direction of the liquid lithium in the liquid lithium conveying area is parallel to the flow direction of the liquid lithium in the divertor target plate. The liquid lithium divertor device can continuously convey liquid lithium to the target plate and make the flow uniform, can improve the spreading of the liquid lithium when flowing along the target plate, obtain a larger spreading area, prevent spattering of the liquid lithium, and conveniently replace the target plate.

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.