111 results about "Nuclear fission" patented technology

A reactor vessel that includes a reactor core mounted within a volume of the reactor vessel, the reactor core comprising one or more nuclear fuel assemblies configured to generate a nuclear fission reaction, a riser positioned above the reactor core, the riser forming a primary coolant flow path, a steam generator thermally coupled to the riser, the steam generator communicatively coupled to a steam turbine through a steam inlet that includes a steam inlet valve, a secondary coolant flow path that extends through the steam generator, the secondary coolant flow path coupled to a coolant pump, and a control system coupled to both the steam inlet valve and the coolant pump, the control system configured to control a power output of the nuclear fission reaction by adjusting one or more parameters of the steam inlet valve or the coolant pump.

A fuel assembly (100) for a nuclear fission reactor system (110). The fuel assembly (100) may comprise a pressure tube (120) comprising an aluminium or aluminium alloy. The fuel assembly (100) may comprise a sleeve member (132), the sleeve member (132) extending along a radially inner surface (134) of the pressure tube (120). The fuel assembly (100) may comprise a fuel compact unit (136). The fuel compact unit (136) may be located within the sleeve member (132)) such that a clearance is maintained between a radially inner surface (139) of the sleeve member (132) and the fuel compact unit (136) to define a sleeve member flow passage (140).

This invention discloses a firecracker-style controlled nuclear fusion and fission synergistic power generation device and method. The power generation device includes a fission-fusion reaction system, a circulating cooling system, and other accessories. The fission-fusion reaction system includes a neutron gun, fuel spheres, a fuel sphere storage and delivery device, and a vacuum reactor. The circulating cooling system includes a circulating fan, a voltage regulator, a steam turbine, a steam generator, delivery pipelines, and a water pump. Other accessories include an energy storage and control system and a vacuum pump. This invention innovatively integrates the start-up mechanism, drawing on the firecracker-style multi-reactor relay concept, combining nuclear fission and nuclear fusion. It utilizes the high temperature and pressure generated by nuclear fission to start nuclear fusion, reducing start-up difficulty and cost. Simultaneously, it efficiently converts and utilizes energy, employing helium for heat transfer. Helium's high thermal conductivity, low density, high specific heat capacity, and chemical inertness allow it to effectively carry away the heat stored in the phase change microspheres, comprehensively collecting and converting nuclear reaction heat energy, thus improving energy conversion efficiency.

The utility model discloses an indirect heating type fuel rod simulation piece which comprises a cladding tube and an electric heating element, and the cladding tube is a corrosion product deposition test surface; the electric heating element is arranged in the cladding tube and is used for simulating heat generated by a nuclear fission reaction of the fuel pellet; high-purity helium is filled between the cladding tube and the electric heating element, and sealing of the fuel rod simulation piece is achieved through end plug welding at one end of the cladding tube and circumferential welding between the cladding tube and the electric heating element. According to the utility model, the actual structural characteristics and surface material properties of the fuel element are retained to the greatest extent while the surface thermal load state of the pressurized water reactor fuel element is simulated, so that the authenticity of corrosion product deposition test simulation and the reliability of obtaining test data are improved; and the method can also be used for experimental research on scale-caused accelerated corrosion after deposition of surface corrosion products.

A fuel assembly 100 for a nuclear fission reactor system comprises: a pressure tube 120 comprising aluminium or an aluminium alloy; a sleeve member 132 located inside the pressure tube 120; and a fuel compact unit 136 located within the sleeve member (132). A clearance gap 137 is maintained between the sleeve member 132 and the fuel compact unit 136 to define a sleeve member flow passage 140. The sleeve member and / or fuel compact unit may comprise silicon carbide. There may be an insulation gap between the pressure tube 120 and the sleeve member 132. The fuel compact unit may define at least one flow passage. The fuel assembly may form part of a nuclear fission reactor system in which a working fluid flows through the sleeve member flow passage and the fuel compact flow passage. The working fluid may comprise nitrogen and water vapour.

The invention provides a nuclear-grade hafnium plate preparation method and a nuclear-grade hafnium plate, and belongs to the technical field of nuclear fission reactor control rod neutron absorber material processing.The nuclear-grade hafnium plate preparation method comprises the steps that nuclear-grade sponge hafnium is adopted as a raw material, the oxygen content of a hafnium cast ingot is controlled within a specific range through a smelting technology, and the more obvious strengthening effect is achieved; and the strength of the finished hafnium plate can meet the nuclear pole requirement. Meanwhile, the deformation resistance of the material is increased, so that the problem that the high-strength hafnium plate is difficult to machine is further solved through optimal combination of forging upsetting, hot rolling, annealing, one-pass cold rolling, intermediate annealing, two-pass cold rolling and finished product heat treatment parameters, and the nuclear-grade hafnium plate with various properties meeting the technical requirements is prepared; the tensile strength and the welding strength of the hafnium plate are improved, the process is stable, and the yield reaches 95% or above.

The invention relates to a method for separating heavy metal cations and radionuclides from aqueous solutions. The method according to the invention can be used to separate dissolved and / or suspended naturally occurring ions or radioactive ions produced by radioactive decay, nuclear transformation reactions such as nuclear fission, or, for example, by activation with neutron radiation, from aqueous solutions.

The present invention relates to the use of at least one oxoacid reducing element, and optionally a salt of the oxoacid reducing element, in a molten chloride fuel salt for a molten-salt nuclear fission reactor (MSR). The present invention also relates to a process of nuclear fission within a molten-salt nuclear fission reactor (MSR), said process being characterized in that it is carried out within the MSR reactor, placed in which is an oxoacid reducing element, and optionally a salt of the oxoacid reducing element. The present invention further relates to a molten-salt nuclear fission reactor (MSR) comprising a molten chloride fuel salt, and a mixture comprising the aluminum metal, and its oxidized form, as an oxoacid reducing element, and optionally a salt of the oxoacid reducing element.

Reactor buildings and vessel systems are disclosed. A nuclear power system includes: a building structure that comprises at least two exterior side walls and two end walls, at least one of the exterior walls angled non-orthogonally relative to a floor of the building structure, the at least two exterior walls and two end walls defining an interior volume of the building structure; one or more nuclear reactor systems mounted at least partially in the interior volume of the building structure; and one or more heat exchanger systems mounted at least partially to at least one of the exterior walls. A nuclear reactor vessel system includes: a nuclear fission reactor; an inner vessel that defines an inner volume sized to at least partially enclose the nuclear fission reactor; and an outer vessel sized to wholly or substantially enclose the inner vessel, the inner vessel being removable from the outer vessel.

A nuclear fission power plant (10) comprising: a nuclear reactor core (20) comprising a fuel system (30) and a moderator (35); a plurality of heat pipes (40) that each at least partially extend within the core; a neutron reflector (70) disposed around the core; a plurality of primary neutronic control elements (50) disposed around the core; a secondary neutronic control element (60) configured to be inserted into a void in the core; a fluid circuit (90) comprising a first heat exchanger (92), a second heat exchanger (96), and a pump (94); and an open Brayton power system comprising: a compressor (102); one or more turbines (104, 106); and a generator (108), and being arranged such that air flows through the compressor, the second heat exchanger and the one or more turbines, wherein the second heat-exchanger is configured to permit heat from the core to be transferred to the compressed air from the compressor, and the one or more turbines drive the compressor and the generator.

A nuclear fission power plant (10) configured for extra-terrestrial use comprising a gas-cooled moderated nuclear reactor core (20) with a metallic fuel (30), a moderator (60), and a containment vessel (40) with a containment vessel inlet (42) and a containment vessel outlet (44). A neutron reflector (70) is disposed around a periphery of the gas-cooled moderated nuclear reactor core, and a plurality of neutronic control elements (50) comprising rotatable control drums disposed around the periphery of the gas-cooled moderated nuclear reactor core. A fluid circuit (90) is configured to receive hot gas from the containment vessel outlet and deliver cooled gas to the containment vessel inlet. An electricity generating system (91) is coupled to the fluid circuit so as to generate an electrical current.

Regarding molten salts used in contact with graphite in nuclear reactors, there is a need for them to be easily maintained under strong reducing conditions without causing graphite degradation. [Solution] Use of a molten salt containing aluminum trifluoride and sodium fluoride as a primary coolant for a nuclear fission reactor, wherein the molten salt comes into contact with graphite and aluminum metals during the operation of the nuclear fission reactor.

CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.

The invention discloses a fission spectrometer used for fission fragment independent yield measurement. The fission spectrometer comprises a flight time detector and a screen grid ionization chamber fixedly connected to an outlet of the flight time detector. The flight time detector and the screen grid ionization chamber are provided with pump interfaces used for being connected with a vacuum pump for vacuumizing, and the flight time detector and the screen grid ionization chamber are each provided with a signal interface and a high-voltage electrical interface which are used for receiving detection signals. The signal interface and the high-voltage interface are respectively connected with the data acquisition system and the high-voltage system through lines; the method is suitable for independent yield measurement of fission fragments of multiple fission nuclides and multiple neutron energy points; according to the integrated device, online measurement of neutron-induced heavy nuclear fission can be achieved, errors caused by chemical treatment and step-by-step measurement in a traditional measurement technology are avoided, the mass resolution of fission fragments can be smaller than 1 amu, and the independent yield of the fission fragments can be obtained while excellent mass resolution is obtained.

To provide a compact reactor unit.SOLUTION: A reactor control system (100) for a nuclear fission reactor system comprising a nuclear reactor unit (300) having a reactor core (302) with a central axis (320) extending along the length of the reactor core (302). The nuclear reactor unit (300) comprises a first region (310) provided in the reactor core (302) and a second region (312) provided on the outside of the reactor core (302). The control system (100) comprises a control duct (200) having a first portion (210) configured to extend through the first region (310) and a second portion (220) configured to extend through the second region (312). The duct (200) is filled with a series of control units (400), and each of the control units (400) is configured to travel along the control duct (200).SELECTED DRAWING: Figure 3

A nuclear fission power plant (10) comprising: a gas circuit (90) to circulate gas; a nuclear reactor core (20) comprising: a fuel system (30) and a moderator (35); the nuclear fission power plant further comprising a neutron reflector (70), a plurality of control drums (50), one or more control rods (60), and a containment vessel (40) substantially surrounding the nuclear reactor core and allowing gas in the gas circuit to flow through both the containment vessel and the core, and an open Brayton power system coupled to the gas circuit via a heat exchanger (92), the open Brayton power system comprising: a compressor (102); a turbine system (104); and a generator (108); the open Brayton power system being arranged such that the turbine system is configured to drive the compressor and the generator.

The utility model provides a device for displaying a first original bullet and a hydrogen bullet in China through a vibration platform, and relates to the technical field of science popularization display devices. Comprising a vibration platform, a display and a control system, a platform is arranged on the periphery of the vibration platform, a guardrail is arranged on the top of the platform, and buttons are arranged on the guardrail; the vibration platform, the displayer and the button are all connected with the control system, audiences stand on the vibration platform and press the button, the button transmits confirmation information to the control system, and the control system controls the displayer to play a first original bullet or hydrogen bomb detonation video in China and controls the vibration platform to simulate original bullet detonation or hydrogen bomb detonation to generate vibration. According to the device, video display and vibration platform interaction are combined, the vibration platform is triggered to vibrate while a video is played, the design of interaction points is ingenious, energy generated by explosion of a first original bullet and a hydrogen bomb in China is visually felt through the vibration platform, and the situation that nuclear fission is utilized flatly and the development prospect of nuclear fusion are visually compared and felt.

The invention discloses a small nuclear reactor heat energy recovery system based on thermoelectric conversion. The system comprises a reactor pressure vessel, a pressure stabilizer, a steam generator, a main pump, a heat exchanger, a cooling water pump, a cooling water inlet, a cooling water outlet and a thermoelectric conversion device, the reactor pressure vessel, the steam generator, the heat exchanger and the main pump are sequentially connected to form a thermal loop of the system, high-pressure water in the thermal loop absorbs heat released by nuclear fission in the reactor pressure vessel, and the cooling water inlet, the cooling water pump, the heat exchanger and the cooling water outlet are sequentially connected to form a cold loop of the system. High-pressure water in the hot loop heats the hot side surface of the thermoelectric conversion device, cooling water in the cold loop cools the cold side surface of the thermoelectric conversion device, heat is transmitted to the cold loop from the hot loop through the thermoelectric conversion device under the driving of temperature difference, and part of heat energy is directly converted into electric energy through thermoelectric conversion. And the heat energy of the small nuclear reactor is recycled.

The invention discloses a solid gain medium fission fragment pumping method and a pumping unit, nuclear fuel fission fragments are used as a pumping source, a solid laser gain medium is used for generating laser, and the solid laser gain medium is a semiconductor laser gain medium. The nuclear fuel fission fragments are used as a pumping source for driving, and the nuclear fission fragment pumping unit for generating laser by a solid laser gain medium is adopted, so that the inherent safety characteristic is ensured, the long endurance is ensured, and the reactor core safety of the energy technology in the unmanned operation process is ensured.

A cooling system (900) for a heat source (500) forming part of a nuclear fission reactor system (110). The cooling system (900) comprises a first coolant reservoir (902) for containment of a first coolant (908), a condenser (904), and a first coolant system (906) configured to deliver the first coolant (908) evaporated from the first coolant reservoir (902) by the heat source (500) to the condenser (904). The first coolant system (906) is also configured to deliver condensate (910) from the condenser (904) back to the first coolant reservoir (902). The cooling system (900) further comprises a second coolant flow intake duct (922) which extends from a second-coolant-flow-intake-duct-inlet (924) to a second-coolant-flow-intake-duct-outlet (926). The cooling system (900) further comprises a second coolant flow exhaust duct (932) which extends from a second-coolant-flow-exhaust-duct-inlet (934) to a second-coolant-flow-exhaust-duct-outlet (936). The first coolant reservoir (902) comprises a first-coolant-reservoir-second-coolant-inlet (928) and a first-coolant-reservoir-second-coolant-outlet (930). The second-coolant-flow-intake-duct-outlet (926) is in fluid communication with the first-coolant-reservoir-second-coolant-inlet (928). The first-coolant-reservoir-second-coolant-outlet (930) is in fluid communication with the second-coolant-flow-exhaust-duct-inlet (934). The second coolant flow intake duct (922), the first coolant reservoir (902) and the second coolant flow exhaust duct (932) are provided in series to define a second coolant flow path (920).

Electrolysis induces cold fusion, producing helium-4. [Solution] A mixture of heavy water D and tritium T is placed in a container and electrolyzed using nickel and palladium electrodes to produce helium. The produced helium is collected in a container.

Reactor buildings and vessel systems are disclosed. A nuclear power system includes: a building structure that comprises at least two exterior side walls and two end walls, at least one of the exterior walls angled non-orthogonally relative to a floor of the building structure, the at least two exterior walls and two end walls defining an interior volume of the building structure; one or more nuclear reactor systems mounted at least partially in the interior volume of the building structure; and one or more heat exchanger systems mounted at least partially to at least one of the exterior walls. A nuclear reactor vessel system includes: a nuclear fission reactor; an inner vessel that defines an inner volume sized to at least partially enclose the nuclear fission reactor; and an outer vessel sized to wholly or substantially enclose the inner vessel, the inner vessel being removable from the outer vessel.

A nuclear fission power plant (10) for extra-terrestrial use, comprising: a nuclear reactor core (20) comprising a metallic fuel (30); a plurality of reactor heat pipes (40) at least partially extending within the nuclear reactor core; a neutron reflector (70) and a plurality of neutronic control elements (50) disposed around the periphery of the nuclear reactor core; a plurality of thermoelectric generators (80); a fluid circuit (90) comprising a heat exchanger (92) and a pump (94), wherein an end of the reactor heat pipes extends into the heat exchanger to transfer heat to a working fluid of the fluid circuit which transfers heat to the thermoelectric generators; a passive radiator (100); and a plurality of radiator heat pipes (86). The thermoelectric generators are thermally coupled to the fluid circuit and to at least one of the radiator heat pipes, which are thermally coupled to the passive radiator.

A nuclear fission reactor system 100 provided with a nuclear reactor unit 200 comprises a moderator fluid tank 202 with a fluid flow inlet 210 and a fluid flow outlet 212. The temperature of moderator

The invention discloses an internal combustion engine system utilizing fission reaction productivity of liquid nuclear fuel and a working method, relates to the technical field of nuclear power, and solves the problems that an energy generation mode of an existing nuclear power device is low in efficiency, needs a large number of auxiliary systems, is too large in scale and is difficult to apply on a large scale. One end of a fuel mixing tank communicates with a liquid fuel storage tank and a working medium storage tank, and the other end of the fuel mixing tank communicates with an internal combustion engine; the internal combustion engine is communicated with the discharge tank; the discharge tank is respectively communicated with the working medium storage tank and the spent fuel storage tank; the control system is in signal connection with the fuel mixing tank and the internal combustion engine. Liquid nuclear fuel is stored in the liquid fuel storage tank; the excitation device in the internal combustion engine excites the liquid nuclear fuel to perform nuclear reaction to generate heat to heat the working medium to expand so as to apply work to the outside. Liquid nuclear fuel and a working medium are mixed and introduced into the internal combustion engine, heat is generated through limited nuclear fission reaction to heat and expand the medium, and a piston acts to generate energy.

A nuclear fission power plant (10) for extra-terrestrial use comprising a nuclear reactor core (20) comprising a metallic fuel (30); a plurality of heat pipes (40), each heat pipe at least partially extending within the nuclear reactor core; a plurality of primary neutronic control elements (50) comprising rotatable control drums disposed around a periphery of the nuclear reactor core; a neutron reflector (70) disposed around the periphery of the nuclear reactor core; a plurality of thermoelectric generators (80); a fluid circuit (90) comprising a heat exchanger (92) and a pump (94), wherein heat is transferred from the nuclear reactor core to a working fluid of the fluid circuit via the heat pipes, and the fluid circuit transfers heat from the heat exchanger to the thermoelectric generators; and a passive radiator (100), wherein the thermoelectric generators are thermally coupled to the fluid circuit and the passive radiator.

To provide a fusion-driven subcritical reactor that is more efficient and safer. [Solution] A fusion-driven subcritical reactor is a nuclear reactor that starts and operates by amplifying neutrons obtained from nuclear fusion and supplying the amplified neutrons to a reactor that holds subcritical nuclear fuel by external neutrons. It consists of a main neutron source that generates DD neutrons through a nuclear fusion reaction, a cascade member that surrounds the main neutron source, separates fusion / fission neutrons, multiplies the fast fission neutrons generated by nuclear fission, and slows down the fast fission neutrons, and a cascade member that surrounds the cascade member and is mainly made of thorium oxide ( 232 It is equipped with a subcritical main fission blanket made of uranium dioxide (ThO2), and a neutron flattening blanket that has a neutron source located around the outer periphery of the main fission blanket to improve the containment of fission neutrons.

This invention provides a passive pressurized water reactor (PWR) nuclear island main building and nuclear power plant. The main building comprises a reactor building, a nuclear auxiliary building, and a nuclear island electrical building. The reactor building provides containment space for the nuclear fission reaction; the nuclear auxiliary building houses radioactive materials and non-radioactive materials preferably placed close to radioactive areas; the nuclear island electrical building houses non-radioactive materials. In a top view, the main building has a rectangular outline. The nuclear auxiliary building and the nuclear island electrical building surround the reactor building, with the reactor building located in the central region of the rectangle. The nuclear auxiliary building and the nuclear island electrical building are located on either side of the reactor building, and their outer outlines together form a rectangle. This passive PWR nuclear island main building and nuclear power plant improves the compatibility of the building layout structure.

A nuclear reactor for maintaining a continuous nuclear fission chain reaction, the nuclear reactor comprising a vessel (1) having an interior (30, 35), the nuclear reactor further comprising in the interior of the vessel: a nuclear reactor core (2); a primary heat exchange circuit (3); a conduit (23) for transporting the internal and external heat exchange medium; a heat exchange device for exchanging heat between the primary heat exchange medium and the internal and external heat exchange media; and at least one controller (50) configured to autonomously control the operation of the nuclear reactor in dependence on data originating within the vessel (1).

A nuclear fission power plant (10) configured for extra-terrestrial use comprising a gas-cooled moderated nuclear reactor core (20) with a metallic fuel (30), a moderator (60), and a containment vessel (40) with a containment vessel inlet (42) and a containment vessel outlet (44). A neutron reflector (70) is disposed around a periphery of the gas-cooled moderated nuclear reactor core, and a plurality of neutronic control elements (50) comprising rotatable control drums disposed around the periphery of the gas-cooled moderated nuclear reactor core. A fluid circuit (90) is configured to receive hot gas from the containment vessel outlet and deliver cooled gas to the containment vessel inlet. An electricity generating system (91) is coupled to the fluid circuit so as to generate an electrical current.