149 results about "Reactor design" patented technology

The invention relates to a superconductive annular air-core reactor structure optimization method, a medium and a program product, and the optimization method comprises the steps: optimizing the structure parameters of a superconductive reactor through an MATLAB and COMSOL joint simulation technology, and carrying out the optimization of the structure parameters of the superconductive reactor through a multi-objective genetic algorithm, thereby achieving the optimization of the structure parameters of the superconductive reactor. Iterative optimization is conducted on structural parameters such as the coil inner diameter, the surrounding radius, the number of turns of the coils, the number of the coils and the number of parallel branches of the electric reactor, the optimization target comprises the minimum strip use amount and alternating current loss, and in the optimal solution set, according to the strip use amount and the alternating current loss, the strip cost and the refrigeration cost are calculated. And finally, outputting an optimal structure parameter meeting a design index so as to realize the minimization of the total cost. Compared with the prior art, the method can be used for structural optimization of the superconducting reactors with different capacities, structural parameters with the lowest cost under different indexes can be obtained by setting constraint conditions, and economic benefits of reactor design are improved.

The invention discloses a reactor core nuclear thermal coupling calculation method based on an embedded physical knowledge neural network. The method comprises the following steps: 1, dividing reactor core nodes of a nuclear reactor; 2, initializing neutron physical field parameters and thermal hydraulic parameters of the reactor core; 3, building, training and storing an embedded physical knowledge neural network model; 4, predicting the neutron number density of each node of the reactor core by using the stored model to obtain neutron flux distribution; 5, calculating reactor core power distribution according to neutron flux distribution; 6, calculating and updating the thermal hydraulic parameters of the reactor core at the tn + 1 moment by using a system analysis program; 7, calculating and updating reactivity of each node of the reactor core; and 8, judging whether the appointed calculation time is reached, if so, ending, otherwise, returning to the step 4. The method is based on an embedded physical knowledge neural network method, an accurate and efficient calculation method is provided for solving distribution of the neutron physical field and the thermal field in the reactor core, and the method has important significance on reactor design optimization.

A long-period fuel management method based on accident fault-tolerant fuel comprises the following steps that a replacement fuel assembly with a first enrichment degree, a second enrichment degree and a third enrichment degree is provided, and 5% lt is provided; a first enrichment degree lt; a second enrichment degree lt; according to the third enrichment degree, accident fault-tolerant fuel is adopted for the fuel replacement assembly; taking out n groups of fuel assemblies in the reactor, putting the n groups of fuel assemblies into a spent fuel pool, selecting a group of fuel assemblies with the highest backup reactivity from the spent fuel pool, arranging the selected group of fuel assemblies in the center of the reactor, and taking (n-1) groups of replacement fuel assemblies and the remaining fuel assemblies of the reactor as reloading groups; calculating an installation sequence of the refueling group according to a reactor design limit value and a safety certification condition, and carrying out installation; and the materials are repeatedly changed every 24 months. According to the method, the fuel circulation period can be prolonged to 24 months, the fuel utilization rate is effectively increased, and the economical efficiency of the nuclear power plant is improved.

A long-term fuel management method based on accident-tolerant fuel, comprising the following steps: providing replacement fuel assemblies with a first enrichment degree, a second enrichment degree, and a third enrichment degree, wherein 5% < the first enrichment degree < the second enrichment degree < the third enrichment degree, and the replacement fuel assemblies adopt accident-tolerant fuel; taking out 69 groups of fuel assemblies in the reactor and putting them into the spent fuel pool, selecting a group of fuel assemblies with the highest reserve reactivity from the spent fuel pool and setting it at the center of the reactor, and taking 68 groups of replacement fuel assemblies and the remaining fuel assemblies in the reactor as a refueling group; calculating the installation sequence of the refueling group according to the reactor design limit and safety certification conditions and installing it; repeating refueling every 24 months. This method can extend the fuel cycle period to 24 months, effectively improve the fuel utilization rate, and improve the economy of nuclear power plants.

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 relates to the technical field of ammonia control and denitrification of kiln flue gas, in particular to an ammonia control and denitrification method for kiln flue gas for preparing cement from carbide slag based on waste heat utilization. According to the technical scheme, the method comprises the following steps that waste heat cooperative utilization is conducted, specifically, flue gas waste heat is subjected to graded utilization through three waste heat recovery systems, specifically, kiln bypass waste heat utilization is conducted, flue gas is extracted from a kiln bypass dechlorination high-temperature area at about 350 DEG C, and the overall energy consumption of the system is reduced; the atomization effect of the calcium nitrate solution is optimized by adopting the nano dispersing agent, and the sulfur resistance of the modified catalyst is combined, so that efficient and stable denitration reaction is realized, ammonia escape is accurately controlled, finally, the flue gas of the kiln can meet the ultralow emission requirement, and secondary pollution to the environment is greatly reduced; the modular reactor design and the dynamic predictive control technology enhance the adaptability of the system to complex working conditions, meanwhile, fuel consumption is further reduced through waste heat recycling and raw flue gas preheating, the service life of equipment is prolonged, and the operation cost of the system is remarkably reduced.

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 discloses hydrogen production equipment and a hydrogen production method based on sodium-catalyzed ammonia cracking, and the hydrogen production equipment comprises a reactor which is a pressure-bearing shell and tube type heat exchange reactor and is internally provided with a plurality of heat exchange tubes filled with a sodium-based catalyst, two ends of the reactor are sealed through a first sealing cover and a second sealing cover, and the first sealing cover is connected with an ammonia storage tank; the second sealing cover is connected with a gas purification separator; the ammonia storage tank is used for storing liquid ammonia and supplying ammonia to the reactor through the booster pump; the gas purification separator is used for separating unreacted ammonia, nitrogen and hydrogen from emissions of the reactor; the temperature control system controls the reaction temperature by adjusting the flow of the heat source gas entering the reactor. A sodium-based catalyst is adopted, and in-situ regeneration of the catalyst is realized through a dynamic circular reaction mechanism; sodium serves as an intermediate medium and is continuously consumed and regenerated in the ammonia cracking process, external supplementation is not needed, the reaction path specificity is high, the byproduct generation rate is low, and the heat transfer efficiency is improved through the design of the countercurrent shell and tube type heat exchange reactor.

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 discloses a thermal hydraulic numerical analysis method and equipment for a nitrogen pressure stabilization reactor, and relates to a combined analysis method of a one-dimensional system level thermal hydraulic analysis program and an equipment internal three-dimensional structure level CFD (computational fluid dynamics) program. Phenomena of nitrogen dissolution, migration, precipitation, accumulation and the like in the nitrogen pressure-stabilized reactor and thermal hydraulic effects caused by the phenomena are subjected to whole-process prediction, and the influence of the phenomena on loop flow heat transfer characteristics and key equipment working performance is further analyzed. According to the method, multi-dimensional and multi-scale computational analysis can be realized, on the basis of not consuming a large amount of computing power resources, the dissolution, migration, precipitation and accumulation behaviors of nitrogen in the coolant and the thermal hydraulic effect caused by the dissolution, migration, precipitation and accumulation behaviors are predicted, and check of a nitrogen pressure-stabilized reactor design scheme and formulation of an operation strategy are supported.

The embodiment of the invention relates to the technical field of numerical simulation of reactors, in particular to a numerical reactor, a method for verifying the design of the reactor by using the numerical reactor and a method for predicting the operation of the reactor, and the numerical reactor comprises a physical thermal structure module which is set to simulate a neutron field, a temperature field and a stress field between reactor cores of the reactor; the fuel material module is arranged to simulate the organizational structure change of the fuel of the reactor in the fission process and the organizational structure change of the material; and the coupling module is configured to couple the neutron field, the temperature field and the stress field of the fuel material module according to the neutron field, the temperature field and the stress field of the physical thermal structure module, and is configured to couple the neutron field, the temperature field and the stress field of the physical thermal structure module according to the organizational structure change of the material and the fuel of the fuel material module. The numerical reactor disclosed by the embodiment of the invention is beneficial to ensuring the accuracy and reliability of the determined organization structure change of the fuel and the material and the neutron field, the temperature field and the stress field between the reactor cores.

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 belongs to the field of organic matter synthesis, and particularly discloses a preparation method of tert-dodecyl mercaptan, which is characterized in that hydrogen sulfide and dodecene are used as raw materials, and an addition reaction is performed under the catalytic action of a solid acid catalyst by adopting a liquid-solid heterogeneous process and a fixed bed reactor to obtain the tert-dodecyl mercaptan. The continuous liquid-solid reaction is realized, the diffusion time of hydrogen sulfide to a liquid phase main body is shortened, the heat capacity and the heat transfer coefficient of a reaction system are improved, the catalytic efficiency of the catalyst and the temperature controllability of the reaction process are improved, and the reactor design is simplified. Under proper operation conditions, the conversion per pass of dodecene is greater than or equal to 85%, the selectivity is close to 100%, the technological process is simple, few three wastes are generated, treatment is easy, and the method is suitable for industrial production.

The utility model belongs to the technical field of new energy photovoltaic silicon material preparation, and discloses a high-density rapid fluidized bed reactor for hydrogenation reduction of silicon tetrachloride. The reactor consists of a high-density rapid fluidized bed, a cyclone separation system and a material returning system, wherein a turbulent fluidization section is connected with a rapid fluidization section through a reducing and reducing section; a first gas inlet, a distribution plate, a gas distributor, a particle feeding hole, a first material return inlet, a second gas inlet and a second material return inlet are sequentially arranged on the cone bottom, the turbulent flow fluidization section and the rapid fluidization section of the high-density rapid fluidized bed; particles separated by the first-stage cyclone separator of the reacted gas-solid mixture return to the turbulent flow fluidization section, and particles separated by the second-stage and above cyclone separators return to the rapid fluidization section. The high-density rapid fluidized bed reactor designed by the utility model has the advantages of full gas-solid contact, rapid heat transfer and mass transfer, higher hydrogenation reaction conversion rate, high operation flexibility and high volume utilization rate.

A syngas reforming exchanger reactor design is described. The reforming exchanger has a head, a shell, and a tubesheet secured a tube bundle. The tubesheet is bolted to the shell, after which the head is bolted to the shell. A seal is configured between the tubesheet and components of the shell. Another seal is configured between components of the head and the tubesheet. In the reformer exchanger design, those seals are maintained under bolted pressure via the bolting of both the tubesheet and the head to the shell. This design improves the integrity of sealing, thereby preventing escape of hot reformed gases from the reformer exchanger reactor during operation.

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 method for selecting a solid-state micro-heap design benchmark accident. The method comprises the following steps of: establishing an event tree and calculating the occurrence frequency of an event sequence according to an originating event list and a corresponding occurrence frequency; obtaining a solid-state micro-stack design reference event; and providing a key safety function list and a PSA modeling system, taking a system which is used as an accident consequence relieving system in all design reference events as a safety related system, and screening out a design reference event which is successfully executed by the safety related system as a design reference accident of the solid-state micro-reactor. According to the method, the structural design characteristics of the solid-state micro-reactor can be effectively analyzed based on risk guidance, design basis accidents are reasonably screened out, and the safety management level of the solid-state micro-reactor is effectively improved. The invention further provides a system for selecting the solid-state micro-reactor design benchmark accident.

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 present invention discloses a high performance SiC f / SiC composite material and its preparation method, which relates to the technical field of composite materials. The method includes obtaining a two-dimensional SiC f / Ti‑Si‑C‑O fiber cloth; SiC obtained by RMI process f / Ti3SiC2 interface phase two-dimensional fiber cloth; SiC f / Ti3SiC2 interface phase two-dimensional fiber cloth is immersed in the slurry suspension to obtain SiC f / Ti3SiC2 interface / TiC‑TiO2 fiber cloth; SiC f / Ti3SiC2 interface / TiC‑TiO2 preform; SiC f / Ti3SiC2 interface / TiC-TiO2 preform is embedded in AlSi alloy powder, and liquid phase siliconization is carried out in a vacuum furnace at 1250~1450℃ for 30~60min using RMI process to obtain high performance SiC for nuclear use. f / SiC composite material. The present invention adopts gas phase and liquid phase combined successive siliconization process to solve the current nuclear SiC f / SiC composite materials have poor air tightness and low thermal conductivity, and can further enhance the material's resistance to radiation amorphization and damage tolerance, thereby improving the SiC f / The structural strength of SiC composite materials during reactor service improves the safety margin of reactor design.

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.

The invention discloses a heat pipe reactor core nuclear thermal characteristic numerical simulation method, electronic equipment and a storage medium, and the heat pipe reactor core nuclear thermal characteristic numerical simulation method comprises the steps: building a neutron physical model according to a reactor core geometric configuration and material parameters given by a heat pipe reactor design scheme; obtaining three-dimensional power distribution of the heat pipe reactor core under the critical working condition; carrying out normalization processing on the output power distribution counting result, and converting the result into a fuel rod axial heat source distribution curve through a polynomial fitting method; and sequentially obtaining heat pipe temperature distribution, reactor core three-dimensional temperature distribution and reactor core three-dimensional thermal stress strain distribution. According to the method, nuclear thermal characteristic calculation software is connected through an external coupling method, thermal characteristic calculation is achieved through an internal coupling mode, and nuclear thermal characteristic coupling calculation of the reactor core of the heat pipe reactor can be achieved efficiently and rapidly. According to the method, the advantages of each piece of calculation software are fully exerted, the reliability of numerical analysis is ensured, and the efficiency of reactor core design work is improved.