94 results about "Reactor design" patented technology

The invention discloses a small modular prismatic high-temperature gas cooled reactor core optimization design method and system based on data driving. The method comprises the following steps: constructing a training data set; a data-driven agent model is trained to replace and execute high-cost simulation calculation; and exploring a design space and generating a group of Pareto optimal candidate solutions by using a multi-objective evolution algorithm and taking the proxy model as a fitness function evaluator. The key feature of the method is a closed loop of iterative verification and model updating: verifying the candidate solution through high-fidelity simulation, if the prediction precision does not meet the convergence criterion, expanding the verified new data point to a training data set, and retraining the agent model. According to the method, the calculation cost can be remarkably reduced, a complex design space can be efficiently explored, and a physically reliable reactor design scheme with better performance can be obtained.

The invention discloses a Bayesian optimization-based single-screw extrusion reactor design method and application thereof. The method comprises the following steps of: determining key structure parameters and process parameters of a single-screw extrusion reactor so as to establish an initial parameterized geometric model; importing the initial parameterized geometric model into simulation software for analog simulation to obtain performance parameters of the reactor model; a parameter communication interface of simulation software and a Bayesian optimization algorithm is realized through a script, performance parameters are used as a target function, and the Bayesian optimization algorithm is used for automatically optimizing the screw pitch, the screw rotating speed and the catalyst dosage of the screw; automatically updating parameters of the reactor model according to an optimization result, and performing simulation calculation again; iterative optimization is carried out until convergence, and finally, the structure parameters and the process parameters of the single-screw extrusion reactor with the optimal performance are obtained. The design method of the single-screw extrusion reactor is high in automation degree, good in optimization precision, high in optimization efficiency and good in application prospect.

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 present disclosure provides an apparatus for producing covetic materials that addresses limitations in conventional covetic material production methods. The apparatus utilizes pulsed RF energy to dissociate carbon-containing fluid into carbon species in a first region of a reactor, while a second region receives metal-containing fluid to form metal species. The downstream arrangement of the first and second regions enables controlled mixing of carbon and metal species, followed by cooling at an output port to form covetic materials. The pulsed RF energy configuration and dual-region reactor design provide enhanced control over the dissociation process and material formation compared to existing production methods.

The invention relates to the technical field of reactor design, and particularly discloses a micro-channel reactor design method and device based on multi-objective Bayesian optimization and a storage medium, and the method comprises the steps: executing parameter sampling operation, and generating an initial parameter combination; executing a physical field simulation operation aiming at the microchannel reactor based on the initial parameter combination, and generating initial simulation information which comprises a plurality of simulation indexes; performing multi-target scoring calculation on the initial simulation information, adjusting the simulation indexes based on a scoring calculation result, and generating adjusted simulation information; optimizing the adjusted simulation information based on a preset iterative optimization algorithm to generate optimized information; and performing configuration design on the micro-channel reactor based on the optimized information. The existing micro-channel reactor is simulated and analyzed from multiple aspects, so that the efficient and rapid micro-channel reactor design is realized.

The invention relates to the technical field of water treatment and resource recovery, in particular to a high-iron-content acid mine water treatment and recycling method based on immobilized biological oxidation and fractional precipitation, which comprises the following steps: S1, a bacterial immobilization stage; s2, an immobilized biological oxidation stage; and S3, a fractional precipitation stage. The method is high and stable in treatment efficiency, bacteria are firmly fixed on a carrier by adopting a bacteria immobilization technology, the loss of the bacteria is avoided, and the biomass and the metabolic activity are improved; waste recycling is achieved, the sludge yield is low, secondary pollution is avoided, the technology is coupled and innovated, and the reactor is reasonable and efficient in design.

The invention provides a reactor internal capable of realizing integral movement of a reactor core, and relates to the technical field of research, development and design of reactor body structures, the reactor internal comprises a hanging basket barrel, a reactor core shroud and a reactor core; the reactor core is arranged in the reactor core shroud; the reactor core shroud is arranged in the hanging basket barrel body, the reactor core shroud is movably connected with the hanging basket barrel body, the reactor core shroud slides up and down in the hanging basket barrel body, and the bottom of the hanging basket barrel body supports the reactor core shroud. According to the invention, the material changing and maintenance efficiency can be effectively improved, the downtime is shortened, the safety is enhanced, the personnel radiation exposure risk is reduced, the inspection and maintenance are convenient, and the service life of equipment is prolonged. The system adapts to advanced reactor design and conforms to the development trend of modularization and high efficiency, and the performance, safety and economical efficiency of the nuclear reactor are remarkably improved through the design of the system.

This invention relates to the field of chemical synthesis technology, specifically disclosing a high-temperature pyrolysis reaction system and its application. The high-temperature pyrolysis reaction system of this invention employs a two-stage reactor design and is filled with a differentiated catalyst. Combined with acetone as an intermediate feedstock between the two stages, it improves the feedstock conversion rate and the selectivity of the target product. The biomimetic integral catalyst solves the problems of poor mass transfer, high pressure resistance, and backmixing caused by traditional packing materials, achieving precise control of the pyrolysis time and inhibiting secondary polymerization and reverse reactions of the product at high temperatures. Through synergistic optimization of reactor configuration, catalyst structure, and separation technology, the entire system effectively suppresses carbon deposition, achieving efficient preparation of dimethyl ketene. This invention forms an integrated high-temperature pyrolysis reaction system from pyrolysis reactor design, catalyst structure design, and improved separation technology, and applies it to the pyrolysis of isobutyric anhydride to produce dimethyl ketene, achieving high feedstock conversion rate and high selectivity of the target product.

The invention discloses a low-loss and water-cooling type high-frequency reactor, belongs to the technical field of high-frequency reactor design, is used for power electronic equipment such as a renewable energy medium-voltage direct-current converter, and solves the problem of low-loss design of the reactor under the requirements of high power, high frequency and high heat dissipation. Comprising a magnetic core, a ceramic water-cooling plate, a coil, a water-cooling pipeline, an upper cover plate, a lower cover plate, a pull rod and a water-cooling connector. The magnetic core is in a U shape, the ceramic type water cooling plates are tightly attached to the two sides of the magnetic core, and the coil is wound on the magnetic core and the ceramic type water cooling plates. And the water cooling pipeline is respectively connected to the water inlet thread opening and the water outlet thread opening of the ceramic type water cooling plate through the water cooling joint. According to the high-frequency electric reactor, the ceramic material water cooling plate is adopted as a heat-conducting medium and an insulating medium, and the magnetic core winding structure is reasonably designed, so that extra eddy current loss generated in the metal water cooling plate due to high-frequency magnetic leakage of a magnetic core air gap is remarkably reduced, and the conversion efficiency of the high-frequency electric reactor is greatly improved.

The application relates to a knowledge-driven multi-agent cooperative reactor scheme demonstration system and a design method, medium and equipment thereof, the system comprising: a knowledge internalization unit for converting unstructured and semi-structured documents into a dynamic knowledge source which can be queried and utilized by a model in real time; a knowledge structuring unit for extracting core entities, relationships and attributes from the knowledge source and constructing a professional knowledge graph of a reactor design field; and a knowledge application unit for constructing intelligent agents and a collaborative working mechanism of multi-professional intelligent agents based on the knowledge source and the knowledge graph, and constructing an intelligent question and answer interface. Through automatic knowledge management and intelligent agent collaborative work, the application significantly reduces the time and effort of manual intervention and improves the efficiency of reactor scheme demonstration.

The invention relates to the technical field of nuclear reactor design, in particular to a safety assembly, a lead-cooled fast neutron reactor and a passive negative reactivity feedback method. The safety assembly comprises a first positioning piece, a second positioning piece and a containing piece. The first positioning piece and the second positioning piece are respectively connected with the accommodating piece so as to position the two ends of the accommodating piece in the linear direction, the accommodating piece is provided with an accommodating cavity for accommodating a coolant, and one end of the accommodating cavity in the length direction is communicated with the outside of the accommodating piece. The safety assembly is applied to the lead-cooled fast neutron reactor to serve as a safety barrier on the periphery of the reactor core, passive negative reactivity can be rapidly introduced, the structure is simple, implementation is convenient and fast, the nuclear reactor design specification and related technical requirements can be better met, and safety and reliability are further improved.

The invention discloses a nuclear reactor neutron flux prediction method based on global conservation constraint, and belongs to the nuclear reactor physics and machine learning crossing field, and the method comprises the following steps: constructing a depth operator network model based on global neutron conservation constraint; collecting solution data of a neutron transport equation or a neutron diffusion equation under different parameters, constructing a training data set, and training the depth operator network model to obtain an optimal model weight; and initializing the depth operator network model by using the optimal model weight, applying the depth operator network model to a neutron transport equation or a neutron diffusion equation under different parameters for solving, and predicting neutron flux distribution in a corresponding region of the nuclear reactor. According to the method, the physical constraint term for describing the global conservation of neutrons is introduced, so that the accuracy and the physical consistency of the DeepONet network for predicting the neutron transport or neutron diffusion solution can be remarkably improved, the generalization ability and the robustness of the model can be enhanced, and the method is particularly suitable for meeting the rapid and high-precision calculation requirements in the fields of reactor design, reactor core analysis and nuclear safety evaluation.

The application discloses a kind of nitrogen pressure regulating reactor thermal-hydraulic numerical analysis method and equipment, through the joint analysis method of one-dimensional system level thermal-hydraulic analysis program and equipment internal three-dimensional structure level CFD program, nitrogen dissolution, migration, precipitation, accumulation and the like in nitrogen pressure regulating reactor Phenomenon and the thermal-hydraulic effect caused thereby are predicted throughout the process, and further analyze its influence on loop flow heat transfer characteristics, the working performance of key equipment.The application can realize multi-dimensional and multi-scale calculation and analysis, without consuming a large amount of computing resources, to predict the dissolution, migration, precipitation and accumulation behavior of nitrogen in the coolant and the thermal-hydraulic effect caused thereby, support the review of nitrogen pressure regulating reactor design scheme and the development of operation strategy.

Reactor configurations may include one or more staged inlets and / or one or more staged outlets for gaseous and solid feedstocks. In one embodiment of the present disclosure, a reactor design for gas-solid reaction with one or more additional outlet for gas and / or solid phase is provided. In yet another embodiment, the design for a gas-solid reactor with one side inlet and two outlets for gas phase is described. In one embodiment, a reactor design with pairs of inlet and outlet for both gas and solid phase is provided. In another embodiment, a reactor design with one or more side inlets but only one outlet for gas phase is provided. In yet another embodiment, a reactor design with two inlets at the top / bottom of reactor and two side outlets for gaseous phase is described. In yet another embodiment, a reactor design with one or more side inlets and outlets for both gas and solid phases is provided.

The invention discloses an optimization method of a multistage reactor with built-in interstage heat exchange units, which comprises the following steps of: establishing P groups of different interstage heat exchange medium distribution proportion sets, and taking a first group of interstage heat exchange medium distribution proportion; initialization is carried out, the outlet temperature and the outlet composition of each catalyst bed layer are calculated according to reaction kinetics, and the cold medium outlet temperature and the hot medium outlet temperature of each heat exchange unit are calculated; the inlet temperature of the first catalyst bed layer is calculated through a weighted average algorithm and compared, if precision is met, convergence is calculated, and if precision is not met, value assignment is carried out again to continue iteration; and comparing the content of the target product in the outlet composition of the P bed layers. According to the method, the calculation amount consumed for solving a complex heat exchange unit is avoided, chemical reaction, flowing and heat transfer in the reactor are subjected to coupling calculation in combination with a'trial calculation-iteration 'solving strategy, the reactor outlet result can be rapidly obtained under the condition that the precision is guaranteed, and model guidance is provided for subsequent operation condition screening and reactor design.

The embodiment of the application relates to the technical field of nuclear reactor design, and particularly relates to a reactor, which comprises: solid fuel arranged in a reactor body, mixed gas input into the reactor body and reacted with the solid fuel to generate gaseous fuel, a reaction degree control element arranged to be capable of controlling the reaction degree of the mixed gas and the solid fuel, and a nuclear reactivity control element arranged to be used for controlling the nuclear reactivity of the gaseous fuel and the solid fuel. The embodiment of the application inputs the mixed gas into the reactor body, makes the mixed gas react with the solid fuel to generate the gaseous fuel, can simplify the supply mode and supply equipment of the reactor fuel in the mode of producing the gaseous fuel on line, improves the economy of the reactor, simultaneously, controls the reaction degree of the mixed gas and the solid fuel by using the reaction degree control element, controls the nuclear reactivity of the gaseous fuel and the solid fuel by using the nuclear reactivity control element, and is favorable for guaranteeing the reliability and stability of the reactor operation.

Embodiments of the present application relate to the technical field of nuclear reactor design, and more specifically, to a method for determining control rod drop time, which is applied to a fast neutron reactor and includes the following steps: obtaining a shutdown signal from the fast neutron reactor and determining the time corresponding to the shutdown signal as a first time; obtaining a drive signal from a drive device, and determining the time corresponding to the drive signal as a second time when the drive signal indicates that a drive parameter of the drive device is lower than a preset parameter threshold; obtaining a rod position measurement signal from a control rod, and determining the time corresponding to the rod position measurement signal as a third time when the rod position measurement signal indicates that the control rod has reached a rod position corresponding to a shutdown depth requirement; and determining the control rod drop time based on the first time, the second time, and the third time. The method provided in the embodiments of the present application determines the control rod drop time based on the obtained first time, the second time, and the third time, without requiring the participation of an operator or operating personnel, and has high measurement efficiency.

This application relates to the field of nuclear reactors, specifically to a reactor comprising: a reactor vessel, a core assembly, a support member, a shielding assembly, a coolant heat exchange and delivery assembly, and a reactivity control assembly. The reactor vessel forms a top opening; the support member provides support for the core assembly within the reactor vessel, and a coolant flow channel is formed between the support member and the reactor vessel for coolant flow; the shielding assembly is disposed within the reactor vessel to provide shielding for the core assembly; the coolant heat exchange and delivery assembly is configured to drive coolant to flow within the coolant flow channel to the core assembly to cool the core assembly, and to guide and cool the coolant flowing out of the core assembly; the reactivity control assembly controls the reactivity of the reactor; the support member also supports the coolant heat exchange and delivery assembly, and together with the coolant heat exchange and delivery assembly, closes the top opening. The reactor components of this application are relatively concentrated and compact, achieving a small reactor design.

The invention relates to the technical field of intelligent water affair treatment, in particular to an intelligent detection method and device for the denitrification efficiency of a denitrification reactor, and the method comprises the following steps: obtaining a to-be-detected image; performing instance segmentation processing on the to-be-detected image to obtain bubble parameters; a denitrification efficiency detection model is constructed and trained; and inputting the bubble parameters into a trained denitrification efficiency detection model to obtain a detection result. According to the embodiment of the invention, the experiment repeatability is ensured through the design of the parallel reactor, the bubble characteristics are accurately extracted in combination with the MaskFreeVIS model, and the nonlinear correlation model is constructed by using the BP neural network, so that the relative error between the detection result and the measured value of the national standard method is controlled within the engineering allowable range, and the actual detection precision requirement is met.

Embodiments described in this disclosure pertain to catalytic or promotion methodologies for the reactive absorption of carbon dioxide (CO2) from ambient air or other gas streams comprising CO2 into alkali metal carbonates, particularly sodium carbonate or sodium carbonate bearing minerals like trona. Key aspects include the utilization of fully carbonated amines, amine carbamates, or carbamate salts as promoter to expedite the reaction between CO2 and alkali metal carbonates, alongside formulations and reactor designs aimed at optimizing CO2 capture efficiency.

The fission reactor has a shell surrounding a reactor space that is a central longitudinal channel, and a plurality of axially extending rings having adjacent rings form an annular cylindrical space in which a plurality of primary axial tubes are located circumferentially. The circumferentially adjacent primary axial tubes are separated by one of a plurality of secondary channels, and a plurality of webbings connect at least a portion of the plurality of primary axial tubes to an adjacent structure. The fissile fuel composition is located in at least a portion of the plurality of secondary channels, and the primary coolant passes through at least a portion of the primary axial tubes. Addition and / or subtraction manufacturing techniques form an integral and single structure for the fuel-loaded reactor space. During manufacturing and construction, the reactor design can be analyzed using a computational platform that integrates and analyzes data from on-site monitoring during manufacturing.

The invention provides a design method of a double-phase composite magnetic material magnetic valve type electric reactor and the electric reactor, and belongs to the technical field of magnetic valve type electric reactor design. A mixed magnetic circuit structure of a double-phase composite magnetic material and a silicon steel sheet is established, and a hard magnetic material and a soft magnetic material are uniformly distributed in a nanoscale ratio of 3: 7; a 0.2 mm accurate air gap is arranged between the two materials to realize magnetic circuit decoupling, the multistage gradient geometric design of a distributed magnetic valve structure is utilized to optimize magnetic flux distribution and calculate an optimal excitation current vector, and a magnetic coupling coefficient calculation function is established to determine winding parameters to realize effective separation of alternating current magnetic flux and direct current magnetic flux. A multi-objective optimization algorithm and a game theory model are adopted to coordinate a balance relation between magnetic flux distribution uniformity and loss control, design parameters are verified through finite element simulation and optimized to meet performance requirements, and the technical problem of high energy loss caused by magnetic flux path coupling of the magnetic valve type reactor is solved.

The invention relates to the technical field of environmental functional material preparation and water treatment, and discloses a photo-thermal interface reactor, a preparation method and application, and the preparation method comprises the following steps: step 1, preparing clay slurry; step 2, mixing a proper amount of the clay slurry obtained in the step 1 with a sodium alginate solution, calcium salt and a gel accelerator, pouring the mixture into a mold, and standing to obtain gel; 3, inorganic metal salt is dissolved in a solvent, and acid is added to promote dissolution; 4, adding a proper amount of the clay slurry obtained in the step 1 into the solution obtained in the step 3, adding a dispersing agent, uniformly stirring, adding a coagulant, pouring onto the gel obtained in the step 2, and standing the gel; and 5, immersing the hydrogel obtained in the step 4 into a reducing agent solution for in-situ reduction treatment to obtain the photo-thermal interface reactor. The photo-thermal interface reactor designed by the invention ingeniously integrates efficient photo-thermal conversion and interface catalytic degradation functions, and realizes synchronous separation and degradation of organic pollutants in sewage by utilizing solar energy.

The utility model discloses an insulation noise reduction structure of an extra-high voltage oil-immersed shunt reactor, which comprises a plurality of layers of insulation partition plates, a cork rubber pad, a non-adhesive laminated wood fastener, a hot-pressed polyester resin plastic laminated board fastener and a lastrum laminated wood bracket, and the two adjacent layers of insulation partition plates are separated by the cork rubber pad. And the insulating partition plate is fixed on the box wall of the extra-high-voltage oil-immersed shunt reactor through the cork rubber pad, the non-adhesive laminated wood fastener, the hot-pressed polyester resin plastic laminated board fastener and the Lushi laminated wood bracket. The insulation noise reduction structure has enough mechanical strength and certain flexibility, integrates the advantages of reliable mechanical structure, reliable insulation, noise absorption and the like, and solves the problems of high ground potential field intensity and low noise attenuation in a high-voltage line end outgoing line area. The low-noise electric reactor has the advantages of being capable of improving the ground insulation strength of the high-voltage line end and absorbing and attenuating noise, and is suitable for the design of low-noise electric reactors with the grade of 750 kV to 1100 kV.

The application discloses a kind of based on data-driven small modular prismatic high temperature gas cooled reactor core optimization design method and system, comprising: constructing training data set;Training a data-driven proxy model is used to replace the execution high-cost simulation calculation;With a multi-objective evolutionary algorithm, and with the proxy model as its fitness function evaluator, to explore design space and generate a set of Pareto optimal candidate solution.The key features of the application are an iterative validation and model updating closed loop: the candidate solution is verified by high-fidelity simulation, and if the prediction accuracy does not meet the convergence criteria, the new data points after verification are expanded to the training data set, and the proxy model is retrained.The application can significantly reduce the calculation cost, efficiently explore the complex design space, and obtain a physically reliable and more optimal reactor design scheme.

The invention relates to the technical field of organic synthesis, in particular to a trichlorfon production device and a trichlorfon production process, the device comprises a first-stage synthesis kettle, a first-stage synthesis kettle condenser, a second-stage synthesis kettle, a second-stage synthesis kettle condenser and a centrifugal machine; a trichloroacetaldehyde feeding hole, a dimethyl phosphite feeding hole and a precipitant feeding hole are formed in the top of the first-stage synthesis kettle, an overflow hole is formed in the upper part of the side wall of the first-stage synthesis kettle, and the top of the first-stage synthesis kettle is connected with a first-stage synthesis kettle condenser through a pipeline; the second-stage synthesis kettle is communicated with an overflow port of the first-stage synthesis kettle through an overflow pipe, and the top of the second-stage synthesis kettle is connected with a second-stage synthesis kettle condenser through a pipeline; and the centrifugal machine is communicated with an overflow port of the second-stage synthesis kettle through an overflow pipe. According to the invention, a continuous synthesis method is adopted, and solid trichlorfon is immediately precipitated and separated out by adding a precipitant; meanwhile, two stages of synthesis kettles are arranged, so that solid trichlorfon is precipitated and separated out more sufficiently while the reaction retention time is ensured, the trichlorfon content is greater than or equal to 98%, and the yield is greater than or equal to 90%.

The invention relates to the technical field of production of high-purity lithium fluoride, and discloses a preparation system and method of nanoscale high-purity lithium fluoride. Comprising the following steps: a primary reaction tower, in which lithium carbonate powder and hydrofluoric acid solution droplets are in contact and mixed reaction to obtain slurry containing lithium fluoride; the second-stage reaction tower is used for carrying out curing reaction on the lithium fluoride-containing slurry from the first-stage reaction tower to obtain a material subjected to the curing reaction; the settling tower is used for carrying out settling separation on the material after the curing reaction from the secondary reaction tower to obtain supernate and concentrated lithium fluoride slurry, and returning the supernate to the primary reaction tower for recycling; and the spray drying tower is used for carrying out spray drying on the concentrated lithium fluoride slurry from the settling tower to obtain the nanoscale high-purity lithium fluoride. According to the method, through specific reactor design and process parameter control, accurate control and automatic adjustment of the particle size of the lithium fluoride product can be realized.

Embodiments described in this disclosure pertain to catalytic or promotion methodologies for the reactive absorption of carbon dioxide (CO2) from ambient air or other gas streams comprising CC2 into alkali metal carbonates, particularly sodium carbonate or sodium carbonate bearing minerals like trona. Key aspects include the utilization of fully carbonated amines, amine carbamates, or carbamate salts as promoter to expedite the reaction between CO2 and alkali metal carbonates, alongside formulations and reactor designs aimed at optimizing CO2 capture efficiency.

The application provides a compact two-step hydrogen production device and method for methane, and relates to the technical field of hydrogen energy.The application combines a hydrogen production reaction of methane staged reforming and a hydrogen production reaction of water vapor conversion, and designs a compact two-step hydrogen production device with a single reactor as the main body.The device switches the input gas through a valve to realize the switching of the two groups of reactions in the two-step hydrogen production process of methane, and can stably and efficiently produce hydrogen at a lower temperature and under isothermal conditions.At the same time, the hydrogen production process in the device mainly involves the hydrogen production of methane staged reforming and the hydrogen production of water vapor conversion, and the combination between the two-step hydrogen production reactions realizes more efficient high-purity hydrogen production.At the same time, compared with the conventional double reactors which are relatively complex, the compact reactor design is improved in scale, reconstruction space and energy saving effect.

This application relates to the field of cooling devices in the pressure vessel containing the reactor core of a nuclear reactor, specifically to a coolant heat exchange and delivery assembly suitable for a reactor and a reactor. The coolant heat exchange and delivery assembly includes a heat exchange and delivery assembly, a drive assembly, and a heat exchange tube assembly. The heat exchange and delivery assembly is configured to form a heat exchange cavity and a drive cavity in fluid communication with the heat exchange cavity. The drive assembly cooperates with the drive cavity to drive coolant flowing from the reactor core assembly to the heat exchange cavity, where it exchanges heat with the heat exchange tube assembly and then returns to the core assembly. The heat exchange and delivery assembly is also configured to form a gas cavity communicating with the reactor's secondary loop condenser. When steam leaks from the heat exchange tube assembly in the heat exchange cavity, the gas cavity and the heat exchange cavity are connected, allowing steam in the heat exchange cavity to enter the secondary loop condenser via the gas cavity. This configuration achieves a relatively compact and integrated integration of multiple functions of the reactor assembly, facilitating miniaturized and compact reactor design.