125 results about "Molten salt reactor" patented technology

A pipe connector for use in high temperature environments, such as those characteristics of molten salt reactors. The pipe connector can be used in any industry that uses pipe connectors, and in particular, can be used in a molten salt system including a reactor requiring a connection rated for a maximum of about 725° C. and about 15,000 psi. The pipe connector may comprise a pin, a seal ring, a retainer ring, a box, a locking nut, and a retaining nut.

A molten salt nuclear reactor includes a vessel and a control blade assembly disposed within the vessel. The control blade assembly includes a drive rod and a control blade. The drive rod further includes an oblique surface wherein vertical motion of the drive rod and its oblique surface causes horizontal motion of the control blade into and out of a reactor section of the molten salt reactor.

A loading system for a molten salt reactor system includes a slug loading assembly. The slug loading assembly includes an inert chamber having an entry port therein that is configured to receive a solid slug. The loading system further includes a chute having a pipe run extending from the entry port and elevationally below the slug loading assembly. The loading system further includes a terminal sieve fluidically coupled with the pipe run opposite the entry port and configured to receive the solid slug via the pipe run. The terminal sieve is positionable with a flow of a liquid molten salt for dissolution of the solid slug therein.

The invention relates to the technical field of hydrogen energy, in particular to a solid oxide electrolytic hydrogen production system and a control method thereof.The electrolytic hydrogen production system comprises water, a waste heat recovery module, a fused salt phase change energy storage module and a solid oxide electrolytic tank, and the waste heat recovery module comprises a water preheater and a steam heater; product gas generated by the solid oxide electrolytic tank passes through the water preheater and the steam heater in sequence; the fused salt phase change energy storage module comprises a fused salt reactor heat release device and a phase change energy storage fused salt reactor for providing heat for the fused salt reactor heat release device; after being powered by the water pump, water sequentially passes through the water preheater, the molten salt pile heat release device and the steam heater to absorb heat, is converted into water vapor and then flows to the solid oxide electrolytic tank; the fused salt phase-change energy storage module stores energy by using high-temperature phase-change mixed salt, and can convert low-ebb and low-price off-peak electricity of a power grid and abandoned electricity such as photovoltaic electricity and wind electricity into heat energy for storage, so that the consumption of electric energy is reduced, the energy utilization rate is improved, and the hydrogen production cost is reduced.

The invention belongs to the technical field of fluid machinery, and particularly relates to a novel tank type molten salt reactor main pump structure. Comprising a driving device, a sealing section, an air cavity section and a working section which are sequentially connected from top to bottom. The driving device is connected with the working section through a rotating rod; the rotating rod is rotatably connected with the sealing section and the air cavity section; the air cavity section comprises a third outer shell, an air outlet pipe and an air inlet pipe penetrate through the side wall of the third outer shell, an air outlet control unit is arranged at the end, close to the third outer shell, of the air outlet pipe, an air inlet control unit is arranged at the end, close to the third outer shell, of the air inlet pipe, and the air outlet control unit and the air inlet control unit are connected with the working section. The gas outlet control unit and the gas inlet control unit perform negative feedback regulation on the molten salt liquid level of the third outer shell, so that the molten salt liquid level is prevented from being in direct contact with the sealing section; the working section comprises an impeller, a guide vane, a fused salt inlet and a fused salt outlet, fused salt enters the third outer shell from the fused salt inlet, then flows into the impeller and the guide vane section through the pump inlet to be pressurized and stabilized, and finally flows out through the fused salt outlet.

A containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

The invention relates to the technical field of heavy oil product treatment, in particular to a method and device for co-production of a carbon material through molten salt pyrolysis of a liquid oil product, and the method comprises the following steps: the liquid heavy oil product is put into an electric heating molten salt reactor through a continuous feeding system, and the molten salt reactor is filled with a molten alkaline molten salt medium; carrying out catalytic pyrolysis reaction on the oil product in a liquid phase environment of the molten salt medium, wherein the oil product stays in the molten salt for 5-10 seconds; the liquid oil product is uniformly cracked in the liquid phase of the molten salt to generate low-carbon hydrocarbon gas, hydrogen and dispersed fine carbon particles, and the carbon particles suspend on the surface under the buoyancy action of the molten salt and are not deposited and gathered; suspended carbon particles are collected from the surface of the fused salt in real time through a mechanical push rod continuous collection system; according to the method, continuous and stable pyrolysis of the heavy oil product and efficient and continuous separation of the product can be realized in the liquid-phase molten salt environment, the production efficiency is improved, and the stability of the product quality is ensured.

The invention belongs to the technical field of high-temperature alloy heat treatment, and discloses a method for improving the hot working performance of a nickel-based high-temperature alloy for a molten salt reactor by combining pre-deformation and homogenization. The method comprises the steps that raw materials of the nickel-based superalloy for the molten salt reactor to be improved are sequentially subjected to vacuum induction melting, pouring and electroslag remelting refining treatment, and an electroslag remelting refined alloy cast ingot is obtained; the electroslag remelting refined alloy cast ingot is sequentially subjected to heating, heat preservation and pre-deformation treatment and is air-cooled to the room temperature, and a pre-deformed cast ingot is obtained; and the pre-deformed cast ingot is subjected to homogenization treatment and air cooling to the room temperature, and the method is completed. The method is a novel heat treatment process combining pre-deformation and high-temperature homogenization, the hot working performance of the alloy is optimized, the high-temperature alloy uniform in structure and excellent in mechanical property is obtained, and application in the field of high-temperature molten salt energy systems is met.

The utility model provides a heat conduction structure and a molten salt reactor cabin. The heat conduction structure comprises a first pipeline, a heat conduction layer and at least one heat pipe, the first pipeline is provided with a first end face and a second end face at two ends; the heat conduction layer is arranged on the periphery of the first pipeline from the first end face in the length direction of the first pipeline. The heat conduction layer is shorter than the first pipeline; a plurality of channels are formed in the end face of the side, away from the first end face, of the heat conduction layer in the axial direction of the heat conduction layer. Two ends of the heat pipe are closed; one end of each heat pipe is arranged in the channel, and the other end of each heat pipe faces the second end face, so that the part, located in the heat conduction layer, of each heat pipe serves as a condensation section, and the part, not located in the heat conduction layer, of each heat pipe serves as an evaporation section in the working state. Fused salt freezing blockage in the fused salt pipeline can be effectively prevented, and the temperature uniformity of the fused salt pipeline is improved; and the dismounting difficulty of the molten salt reactor cabin through-wall pipeline can be reduced, so that the heat conduction structure is easy to maintain, and the safety and the reliability of the molten salt reactor cabin are improved.

A containment system for an integral molten salt reactor includes a sealed containment structure defining a containment volume. The containment structure includes a fission product adsorbing / absorbing material. The containment system further includes an integral molten salt reactor housed fully within the containment volume of the sealed containment structure. The integral molten salt reactor may permit circulation of a fuel salt therein being heated by fission reactions, and allow for the export of heat from said fuel salt.

A deployment system for a molten salt reactor includes a reactor module, a cooling module, a coolant preparation module, a fuel shipping module, and a fuel preparation module. Each of the reactor module, the cooling module, the coolant preparation module, the fuel shipping module, and the fuel preparation module may be supplied to a deployment site. Using the coolant preparation module, a coolant salt held within the reactor module may be transferred to the cooling module. Using the fuel preparation module, a fuel salt held within the fuel shipping module may be transferred to the reactor module.

The invention belongs to the technical field of fluid machinery, and particularly relates to a novel fused salt reactor main pump structure with an air cavity, which comprises an air cavity section and a working section, the air cavity section comprises a first outer shell and an air cavity, the working section comprises a second outer shell and a working cavity, the air cavity is arranged in the first outer shell, and the working cavity is arranged in the second outer shell. A second outer shell is detachably arranged at the bottom of the first outer shell, the air cavity communicates with the working cavity, a rotating rod rotatably penetrates through the top of the first outer shell, and the working end of the rotating rod penetrates through the air cavity and is located in the working cavity; a liquid level measuring component and a space telescopic component are detachably arranged on the inner wall of the air cavity and jointly form a pressure adjusting device, the number of the pressure adjusting devices can be adjusted according to specific conditions, the liquid level measuring component is connected with the space telescopic component, and the liquid level measuring component is used for monitoring the height of molten salt. The space telescopic component expands / contracts according to the height of the fused salt, the space size of the air cavity section is adjusted, accordingly, the air pressure in the air cavity section is adjusted, and finally negative feedback adjustment on the height of the liquid level of the fused salt is achieved.

The invention discloses a high-temperature damage in-situ characterization method for a composite material for a molten salt reactor based on an acoustic emission technology, and relates to the field of damage characterization of the composite material for the molten salt reactor, and the method comprises the following steps: preparing a C / C composite material under an approximate molten salt reactor working condition; stretching the prepared C / C composite material to obtain a time-stress curve in the stretching process; controlling a laser spot to completely cover the stretching section, and collecting the change condition of an acoustic emission signal; and after the change condition of the acoustic emission signal is correlated with the time-stress curve, judging and representing the change of the internal microstructure of the C / C composite material before and after molten salt infiltration according to a correlation result. According to the method, the internal damage of composite material components with different scales and different shapes in the performance evaluation stage before service under the working condition of the molten salt reactor can be effectively monitored, and the change of the internal microstructure of the material can be analyzed by combining the change of the characteristic frequency of the acoustic emission signal with the tensile curve, so that the method has important engineering practical significance.

The invention relates to a method for machine learning aided design of a structural alloy for a fourth-generation thorium-based molten salt reactor, and belongs to the technical field of artificial intelligence auxiliary material design. The method comprises the steps that S1, an alloy component machine learning model for phase composition prediction is established, specifically, based on known alloy sample data, the sample data comprise alloy element content and corresponding phase composition information, and the machine learning model used for predicting alloy phase composition is established; s2, screening an initial alloy component space through phase composition constraint conditions; s3, secondary screening of alloy components based on thermodynamic simulation; s4, alloy sample preparation and solid solution homogenization treatment; s5, carrying out a mechanical property test; and S6, experimental result feedback and machine learning model closed-loop updating are carried out. According to the method, the artificial intelligence technology and the traditional alloy design theory are organically fused, an efficient and reliable new path is provided for research and development of key structural materials for the fourth-generation thorium-based molten salt reactor, and the important scientific research value and the engineering application prospect are achieved.

The application provides a graphite molten salt reactor, a graphite molten salt reactor system and a use method thereof. The graphite molten salt reactor comprises a graphite assembly, the graphite assembly is divided into multiple layers in the height direction of the graphite molten salt reactor, and each layer of graphite is isolated from each other. The graphite molten salt reactor system comprises the above graphite molten salt reactor. The graphite molten salt reactor, the graphite molten salt reactor system and the use method thereof can change the pressure of the molten salt in the graphite molten salt reactor and make the molten salt flow out of the graphite molten salt reactor naturally without the aid of other devices by dividing the graphite into multiple layers, reducing the pressure of the molten salt flowing through the graphite, and opening and closing the components such as pumps and valves.

The invention provides a molten salt reactor radioactive gas removal device which comprises a main loop module, a gas injection module, a tail gas analysis and treatment module and an observation module, one end of the main loop module is connected with the gas injection module, the other end of the main loop module is connected with the tail gas analysis and treatment module, and the observation module is connected with the tail gas analysis and treatment module. The main loop module comprises a bubbler and a separator, the bubbler is filled with liquid for dissolving gas, and the observation module is arranged at a visual window on the side of a body of the bubbler and the separator; when the radioactive gas is removed, cavitation microbubbles and carrier gas microbubbles which are used for dissolving the radioactive gas are separated out by the bubbler, the cavitation microbubbles and the carrier gas microbubbles form a gas core by the separator, and the gas core is treated by the tail gas analysis and treatment module. According to the invention, deep dissolution and gas removal can be realized, the system sealing performance is good, the gas can be ensured not to leak, and the safety of operators and the environment is ensured.

A metal-organic framework coating may be employed in a molten salt reactor system to capture gaseous fission products produced as a consequence of operation. The metal-organic framework coating may include one or more metal-organic frameworks configured to capture certain fission products based on the need, for example tritium fluoride, tritium gas, and hydrogen fluoride. The one or more metal-organic frameworks may be immobilized onto a substrate and formed into a coating covering the substrate. In many cases, the substrate is the stainless-steel surfaces of reactor enclosures and vessels. In other cases, the substrate may be suspended into a headspace of a vessel of a salt-bearing component, or may be included in an off-gas processing system of a reactor system.

The present invention relates to a method of operating an MSR, said MSR comprising a reactor core, a fuel loop for molten fuel salt providing a flow path of molten fuel salt into the reactor core through a reactor core inlet and out of the reactor core through a reactor core outlet, said method comprising the steps of: providing at least one location mi on the fuel loop at a distance Li measured along the flow path from the reactor core outlet, wherein the one or more locations mi is outside the reactor core, and the one or more locations mi is shielded from the reactor core measuring the neutron source strength at the one or more locations mi obtaining one or more calculated operating parameters by calculation with input of the value of the measured neutron source strength at one or more locations mi.

A molten salt reactor system may produce fission products, such as molybdenum-99, which may be extracted by an extraction system. The extraction system may be configured to sparge the molten fuel salt with an inert gas to dislodge gaseous fission products from the molten fuel salt, so that the gaseous fission products flow through an off-gas outlet into a gas transfer assembly. The example extraction system may also include introducing a gaseous halogenating agent to prevent the fission products from depositing on a pipe surface of the gas transfer assembly. The gaseous fission products may flow from the gas transfer assembly to a carboy containing an aqueous solution, to process and / or filter the fission products. The resulting solution containing processed fission products in the carboy may be further distilled into final, usable products.

Fission reactions within a molten salt reactor may produce gaseous fission products. These fission products may be removed through a variety of methods. However, proper removal of such fission products requires a thorough understanding of the proportion of gaseous space to fluid space within the component being interrogated, known as the void fraction. The present invention provides a means for determining the void fraction within such a component utilizing an enrich cadmium zinc telluride detector to produce collimated radiation data. The collimated radiation data may then be used to compute a mean void fraction across the domain being interrogated.

A molten salt fission reactor. The reactor includes a reactor core including a plurality of fuel tubes. Each fuel tube contains a fuel salt and a gas interface. The fuel salt is a molten salt of one or more fissile isotopes. The gas interface is a surface of the fuel salt that is in contact with a gas space during reactor operation. The reactor also includes a fuel salt cooling system configured for cooling the fuel salt. The cooling system includes a heat exchanger and a coolant tank. The coolant tank contains a coolant liquid in which the fuel tubes are at least partially immersed. The heat exchanger is for extracting heat from the coolant liquid. The fuel salt cooling system is configured such that, during reactor operation, for all points within the fuel salt within each fuel tube except at the respective gas interface:

The application provides a graphite processing method for blocking molten salt and molten metal infiltration, comprising the following steps: S1: providing a thermosetting resin monomer or oligomer solution, adding a small amount of catalyst to the solution to form a precursor, and immersing the precursor into graphite pores; S2: converting the precursor immersed in the graphite pores into organic nanostructures through solidification and drying; and S3: carbonizing the organic nanostructures in the graphite pores at a temperature higher than 500 DEG C to form carbon nanostructures, so that a graphite capable of blocking molten salt and molten metal infiltration is obtained. The processing method provided by the application has the advantages of simple process, difficulty in failure, and no change in the performance of the base material, compared with the traditional surface coating, resin and other impregnation methods, and has obvious advantages over other processing methods when used for processing the graphite in a molten salt core, and has little influence on the mechanical, thermal and radiation behaviors of the graphite, so that the cost caused by the reevaluation of the graphite material can be saved or reduced.

A molten salt reactor system includes a fuel salt system and a coolant salt system. The fuel salt system is configured to circulate a molten fuel salt through a molten salt loop. The coolant salt system is configured to circulate a coolant salt through a coolant loop. The molten salt reactor system further includes a heat exchanger arranged along the molten salt loop and the coolant loop. The heat exchanger is configured to transfer heat from the molten fuel salt of the molten salt loop to the coolant salt of the coolant loop. The heat exchanger is configured to permit gravitational draining of at least one of the molten fuel salt or the coolant salt upon a shutdown event.

Disclosed is a reactor thermal management system. A molten salt reactor vessel and a second component (e.g., a drain tank) fluidly coupled with the molten salt reactor vessel are configured to receive a flow of a molten salt therewith. The reactor thermal management system includes an internal shield or vessel encompassing the molten salt reactor vessel and the second component, the internal shield or vessel defining a first thermally insulative region therein. The internal shield or vessel is configured to maintain the first thermally insulated region above a melting temperature of the molten salt during operation of the molten salt reactor vessel.

The application discloses a device and method for removing water and oxygen from base graphite, which comprises a heating cabin, a vacuum system, an inert gas supply air path system, a trace water and oxygen test system and a storage box. The heating cabin is internally provided with a heating element and at least one tray for placing base graphite. The vacuum system is used for extracting gas in the heating cabin to promote the removal of water and oxygen. The inert gas supply air path system is used for continuously supplying air to purge the heating cabin and remove water and oxygen through a cold trap and a carrier tape. The trace water and oxygen test system is used for continuously sampling and measuring water and oxygen content. The storage box is arranged adjacent to the heating cabin and used for storing the processed base graphite, preventing the base graphite from being contaminated during storage and keeping the water and oxygen content in a target range. The method provided by the application can effectively remove water and oxygen in the base graphite without damaging the structure of the base graphite, guarantee the stability and safety of fuel elements in a high-temperature environment, and is particularly suitable for the manufacture of fuel elements in a fourth-generation nuclear reactor, such as a solid fuel molten salt reactor.

The utility model provides a compact type fused salt heat exchange device which comprises a fused salt pump assembly and a heat exchange assembly, the fused salt pump assembly is communicated with the heat exchange assembly, the heat exchange assembly comprises a heat exchange unit, the heat exchange unit comprises a spiral heat exchange tube bundle, the spiral heat exchange tube bundle is provided with a plurality of spiral heat exchange tubes, and the spiral heat exchange tubes are arranged in a winding mode. The spiral heat exchange tubes in the spiral heat exchange tube bundle are arranged in a winding mode, the heat exchange area can be effectively increased, so that the heat exchange power is improved, compared with a traditional straight tube structure, the turbulent flow effect can be formed when fused salt flows through at the low flow speed, and the formation of turbulent flow is beneficial to enhancing the heat transfer coefficient; and the temperature gradient problem possibly caused by non-uniform flow is reduced. In addition, the parallel structural design of the multiple spiral heat exchange pipe assemblies can be more compact in structure, the occupied area of heat exchange equipment can be reduced, an efficient and compact integrated structure is provided for the molten salt heat exchange device, and the spiral heat exchange device is suitable for being applied to a molten salt reactor system with limited space.

The invention discloses a structural alloy for a molten salt reactor and a component design method of the structural alloy, and belongs to the technical field of multi-principal-element high-entropy alloy materials. The method comprises the following steps: determining the molar content of chromium according to the fluorination corrosion resistance and high-temperature oxidation resistance of the Hastelloy N alloy; the molar content of nickel is determined according to the nickel in the overlapped non-telluride area of the Hastelloy N alloy and the 316 alloy and the thermodynamic activity relation of nickel and chromium; the iron and the molybdenum respectively meet the thermodynamic activity relation with the chromium and are in a non-telluride area of the alloy, the molar content of the iron is determined according to the fluoridation dissolution resistance of the iron in the 316 alloy, and the molar content of the iron and the molybdenum is determined according to the stable phase structure of the molybdenum in the alloy at the temperature of 1000 DEG C as follows: more than 90% of a face-centered cubic solid solution main phase and less than 10% of a hard precipitated phase; and finally obtaining the structural alloy for the molten salt reactor. The structural alloy for the molten salt reactor, which is obtained by the method, has excellent corrosion resistance.

Systems, methods, and techniques disclosed and contemplated herein relate to processing high level radioactive waste (HLW). Exemplary techniques are applicable to various fuel types, such as metal / chloride salt HLW streams from pyroprocessing of sodium bonded metallic fast reactor fuel; metal and halide salt HLW from molten salt reactors; and SiC / pyrolytic carbon from mechanically breached TRISO (tri -structural isotropic particle fuel) kernels with oxide fission products (FPs) from reprocessing. Exemplary waste forms are cermets.

A system for nuclear power generation can include an accelerator-driven subcritical nuclear reactor that operates using molten-salt fuel. The reactor includes a target positioned to receive a proton beam and to be cooled by the molten-salt fuel. A voltage signal is applied to an electrode in contact with the molten-salt fuel in the reactor for controlling corrosion of the target and other portions of the reactor. In one embodiment, the target is used as the electrode. In another embodiment, an electrode other than the target is used.

The application relates to a kind of passive residual heat removal systems of fuel salt discharge tank, heat transfer working medium is solid at room temperature and is liquid after heating, the passive residual heat removal system includes fuel salt discharge tank, salt discharge pipe, natural circulation loop, air cooler and circulation maintaining heat exchange device, fuel salt discharge tank is communicated with nuclear reactor core by salt discharge pipe, fuel salt discharge tank is communicated with air cooler and circulation maintaining heat exchange device respectively by natural circulation loop;Wherein, circulation maintaining heat exchange device is in thermal contact with molten salt reactor main loop pipeline, to compensate the heat loss of passive residual heat removal system by the heat energy of normal working loop.According to the passive residual heat removal system of the application, heat transfer working medium is not water, in the normal operation of reactor, it is standby state, maintain natural circulation fluid in molten liquid state and slowly natural circulation, once accident occurs, the fuel salt of reactor core is discharged into discharge tank, and the natural circulation fluid of molten liquid state can quickly establish natural circulation to remove decay heat.