184 results about "Molten salt reactor" patented technology

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.

A molten salt reactor system includes a fluid level control system configured to circulate a molten salt through a molten salt loop including an experimental tank, a sump tank, and a drain tank. The fluid level control system further includes a plurality of level sensors, pressure transducers, and electronic pressure regulators fluidically coupled with the fuel salt system. The fluid level control system is configured to receive cover gas pressures in the headspaces of the tanks and calculate target fluid height setpoints for each of the tanks. The fluid level control system further invokes the electronic pressure regulator to iteratively adjust the cover gas pressures of the tanks to achieve and maintain a target fluid level in the experimental tank.

The present invention is directed to a fission product extraction system operable to capture and extract fission products from a flow of irradiated fueled molten salt of a molten salt reactor. The example extraction systems described herein utilize electroless deposition to chemically plate fission products onto a metallic structure. The metallic structure may be partially coated with a reducing agent, such as beryllium to provide an electron source for the fission products. The metallic structure may be a component of an extraction system designed to facilitate submersion of the metallic structure into the flow of molten salt. The extraction system may also be designed to facilitate removal of the metallic structure without requiring a shut down or slowdown of the reactor system.

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.

The invention belongs to the field of heat exchangers, and discloses a Stirling engine heat exchanger for a molten salt reactor and a Stirling engine, the Stirling engine heat exchanger for the molten salt reactor comprises a heat exchanger shell, a liquid inlet is formed in the top of the heat exchanger shell, and a liquid outlet is formed in the side wall of the bottom of the heat exchanger shell; the working medium cylinder is hermetically connected with the heat exchanger shell; the multiple first baffle plates are arranged in the heat exchanger shell at intervals in the height direction of the heat exchanger shell, and first channels are formed between the outer side walls of the first baffle plates and the inner side wall of the heat exchanger shell; a second baffle plate is arranged between every two adjacent first baffle plates, and a second channel is formed in the center of each second baffle plate; a plurality of U-shaped heat exchange pipes are arranged in the heat exchanger shell in an array mode along the circumference and penetrate through the first baffle plate and the second baffle plate, and the two ends of each U-shaped heat exchange pipe are inserted into the working medium barrel correspondingly. By arranging the baffle plates, the flowing direction of fused salt and a working medium is changed from parallel flowing to staggered flowing, the convective heat transfer coefficient of the fused salt side is increased, and the heat exchange efficiency is improved.

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.

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 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 field of nuclear reactor engineering design, and discloses a molten salt reactor loop system and a molten salt reactor, the loop system comprises a molten salt heat exchanger and a molten salt pump; the molten salt heat exchanger is provided with a supporting flange; the molten salt pump is provided with a pump tank flange; the molten salt reactor loop system further comprises a coupling flange, and the coupling flange is connected to the lower portion of the supporting flange and the lower portion of the pump tank flange, so that the molten salt pump is located on the peripheral side of the molten salt heat exchanger. According to the molten salt reactor loop system, the molten salt heat exchanger and the molten salt pump are connected into a whole which is arranged left and right through the connecting flange, so that the structure of the molten salt reactor loop system is compact, the molten salt pump is directly arranged on the peripheral side of the molten salt heat exchanger, and the molten salt pump and the molten salt heat exchanger can be communicated through a short pipe; and the complexity of pipeline arrangement of the whole system is reduced.

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.

The invention relates to a device and a method for measuring neutron shielding capability of concrete at high temperature, the device comprises a neutron emitter, a shielding device and a neutron receiver, the neutron emitter is located at a first side of the shielding device, and the neutron receiver is located at a second side, opposite to the first side, of the shielding device; the shielding device comprises a support and samples, the samples are arranged on the support, the samples comprise three test samples and a measurement environment background sample, the three test samples are a control group, a cylindrical concrete test piece and a detection piece group in sequence, and the cylindrical concrete test piece group is arranged on the support. An ultrahigh heat-conducting polymer film layer and a stainless steel alloy sleeve layer are sequentially arranged on the outer side of the cylindrical concrete test piece, and the detection piece comprises a temperature sensor and a strain gauge. The neutron shielding capability is measured by adopting the measuring device, so that the neutron shielding capability of the new-generation molten salt reactor nuclear energy system warehouse concrete is effectively measured, and the thickness design of the neutron shielding concrete in engineering construction is facilitated.

The invention relates to the technical field of hydrogen energy, in particular to a methanol reforming hydrogen production system and a control method thereof.The system comprises a methanol-water mixing module, a fused salt phase change energy storage module, a reforming reaction module and a post-treatment module which are sequentially communicated; the fused salt phase change energy storage module comprises a phase change energy storage fused salt reactor as well as a heat release device I and a heat release device II which are arranged in the fused salt reactor, the output end of the methanol-water mixing module is connected with the heat release device I, and the output end of the heat release device I is connected with the reforming reaction module; the reforming reaction module comprises a reforming reactor with a built-in axial heating tube bundle, a catalytic reaction cavity is formed between tubes of the axial heating tube bundle, an in-tube channel of the axial heating tube bundle and the second heat release device form a circulation loop, and a heat transfer working medium is arranged in the circulation loop. By combining phase change energy storage and an efficient heating working medium circulation loop, the problem that the temperature of a catalyst is not constant in a traditional hydrogen production process is solved, and the reaction efficiency, the hydrogen yield and the hydrogen purity of the system are fundamentally improved.

The present invention relates to a reactor construction (1) comprising an upper compartment (2) above a drain tank compartment (3), said upper compartment (2) comprising: a molten salt reactor (MSR) (4), comprising a reactor vessel (5) comprising a molten fuel salt (6); a molten salt drain system connected to the reactor vessel (5); said drain tank compartment (3) comprising: one or more drain tanks (10) in communication with the molten salt drain system; a buffer water tank (15) comprising an inner wall (16) and an outer wall (17) and buffer water (21) in the gap between the inner wall (16) and the outer wall (17) of the buffer water tank (15), said buffer water tank (15) surrounding the one or more drain tanks (10), wherein a first piping structure (22) is defining a circuit for at least part of the buffer water (21) and comprising a heat exchanger (23) in thermal contact with a reservoir water tank (30), said reservoir water tank (30) being at a level above the buffer water tank (15), said reservoir water being in thermal contact with an environment and / or a second piping structure (24) is defining a circuit for at least part of the buffer water (21) and comprising a heat exchanger (25) in thermal contact with an environment, said heat exchanger (25) being at a level above the buffer water tank (15) and / or a seawater heat exchanger (26) in thermal contact with the buffer water (21) and seawater, said seawater heat exchanger (26) being located below seawater level outside the outer wall (17) of the buffer water tank (15).

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 discloses a small liquid-solid dual-fuel molten salt reactor core loaded with a cross spiral fuel, and relates to the technical field of nuclear reactor engineering. The reactor core of the small liquid-solid dual-fuel fused salt reactor loaded with the cross spiral fuel comprises two parts, namely an active area and a control drum, the control drum comprises a reflecting layer and a control drum absorbing material, the reflecting layer is made of beryllium oxide, and the control drum absorbing material is boron carbide with the boron 10 enrichment degree of 100%; the active area is composed of a fuel element and a fluoride salt coolant, and the whole active area is packaged in a shell made of Zr-4; the fuel element is in a cross spiral shape and is arranged in a regular hexagon shape, the fuel element is composed of an axial reflecting layer, fuel, a He cavity and an Re absorber, and the fuel is UC solid fuel with the U-235 enrichment degree being 45.684 wt.%; the material of the fluoride salt coolant is 7LiF-KF-UF4 (49.55 to 49.55 to 0.9 mol%), wherein the enrichment degree of U-235 in the UF4 is 30 percent by weight. According to the invention, the reactor core power density is further improved and the fuel peak temperature is effectively reduced while the reactor core heat is ensured to be discharged in time.

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.

A method and system for calibrating nuclear instrumentation of a reactor is disclosed. The system comprises a reactor configured to operate at a low power level and an external heater configured to heat the reactor to its operating temperature and maintain the reactor in a critical state. The reactor maintains its temperature at a steady state by repeating steps of reducing the heater's power and increasing the reactor's power by changing one or more reactivity settings, wherein the reduced heater's power is compensated by using the increased power generated by the reactor itself. The nuclear instrumentation is configured to measure the reactor's output power and compare it with the calculated reactor's power. Based on the discrepancy between the calculated power and the measured power exceeds a threshold; and the nuclear instrumentation is appropriately calibrated by adjusting one or more settings.

The invention relates to the technical field of nuclear power systems, and provides a power generation system based on Brayton cycle and a ship. The power generation system based on the Brayton cycle comprises a molten salt reactor, a first heat pipe, a second heat pipe, a first Brayton cycle system and a second Brayton cycle system, wherein the first heat pipe and the second heat pipe are respectively connected with the molten salt reactor; the first Brayton cycle system is connected with the molten salt reactor through a first heat pipe, the second Brayton cycle system is connected with the molten salt reactor through a second heat pipe, and heat energy is transmitted to the first Brayton cycle system and / or the second Brayton cycle system to be converted into electric energy. The two Brayton cycle systems are arranged in parallel, heat energy is converted in the first Brayton cycle system and / or the second Brayton cycle system, and the power of each cycle system is reduced; when one Brayton cycle system breaks down, the other Brayton cycle system can operate normally, and the reliability of the system is improved.

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.

A molten salt reactor system includes a fluid level control system configured to circulate a molten salt through a molten salt loop including an experimental tank, a sump tank, and a drain tank. The fluid level control system further includes a plurality of level sensors, pressure transducers, and electronic pressure regulators fluidically coupled with the fuel salt system. The fluid level control system is configured to receive cover gas pressures in the headspaces of the tanks and calculate target fluid height setpoints for each of the tanks. The fluid level control system further invokes the electronic pressure regulator to iteratively adjust the cover gas pressures of the tanks to achieve and maintain a target fluid level in the experimental tank.

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.