73 results about "Nuclear fission" patented technology

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.

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.

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 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.

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.

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

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.

A first invention describes a molten salt nuclear reactor system and a method of controlling a nuclear reactor, the molten salt nuclear reactor housed in a closed vessel of the molten salt nuclear reactor system, the molten salt nuclear reactor comprising: a reactor core, a circulation pump, a discharge tank, a controller, and a liquid circuit for circulating liquid through the reactor core, wherein the controller is configured to autonomously stop reactor operation by allowing liquid to be discharged into the discharge tank under the influence of gravity if at least one reactor parameter differs from an acceptable operating value, and / or wherein the controller is configured to control the discharge of the liquid into the discharge tank under the influence of gravity. The controller is configured to initiate reactor operation by activating the circulation pump to pump liquid from the discharge tank to the liquid circuit if all reactor parameters meet acceptable operating values. A second invention describes a molten salt nuclear reactor and a method 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 inside the vessel: a nuclear reactor core (2); the molten salt primary heat exchange loop (3) comprises a molten salt primary heat exchange medium pump; at least one sensor (9, 22, 41, 49) and a base, 59, 79), the at least one sensor being configured to provide a signal representative of an operating state of the nuclear reactor; a primary heat exchanger (10) through which the primary heat exchange circuit passes; and a circuit breaker circuit arrangement (18, 28, 68) comprising a circuit breaker (19, 29, 69) and configured to connect at least one of the electrical and / or electronic components (5, 15, 45) in the interior to a power source (53) within the container (1) and to connect at least one of the electrical and / or electronic components (5, 15, 45) in the interior to a circuit breaker (19, 29, 69). 45) being disconnected from the power source (53) within the container; the circuit breaker (19, 29, 69) has an open state and a closed state; the circuit breaker circuit arrangement (18, 28, 68) is connected to at least one sensor (9, 22, 41, 49, 59, 79); and the circuit breaker circuit arrangement (18, 28, 68) is configured to open the circuit breaker (19, 29, 69) when the signal from the at least one sensor (9, 22, 41, 49, 59, 79) exceeds a safety threshold.

This invention relates to a nuclear-targeted multimodal imaging diagnostic probe with BNCT therapeutic efficacy, its preparation, and its application, belonging to the fields of biomedicine and nuclear medicine technology. This boron drug contains... 10 Using acetylacetone difluoroborate as the parent nucleus, this invention endows the tumor with nuclear targeting ability by introducing N- or S-containing heterocyclic structures, while utilizing its conjugated structure to provide fluorescence / photoacoustic dual-modal imaging functionality. Based on this, the invention achieves three core functions: first, through fluorescence / photoacoustic dual-modal imaging, it enables the visual localization and real-time monitoring of tumor sites; second, by leveraging the binding of nuclear targeting groups to nuclear DNA / RNA, it... 10 B is precisely delivered into the nucleus, significantly improving the killing efficiency of BNCT; thirdly, thermal neutron irradiation is performed under imaging guidance, triggering... 10 The B(n,α)⁷Li nuclear fission reaction ultimately enables high-precision integrated diagnosis and treatment. This invention also discloses a method for preparing this probe, which has promising clinical application prospects.

The application discloses a kind of magnetohydrodynamic power generation device, it relates to nuclear reactor technical field, including protective shell, inside along axial through power generation passage, outside is equipped with current coil, current coil is used to provide magnetic field;Pump, communicate with power generation passage by pipeline, pipeline is filled with Ar gas, pump is used to pressurize Ar gas;Core, it is arranged in power generation passage inside along axial, core is formed by multiple fuel plates with the shape of Chinese character well, the fuel in fuel plate generates multiple fission fragments after nuclear fission;Fuel plate thickness is less than the range of fission fragment;Reflective layer, cover in the outer wall of core, including two symmetrically arranged half-ring metal electrodes.The application utilizes the fission fragment generated by nuclear reactor to bombard rare gas and ionize the gas, and the ionized gas generates electricity through the magnetohydrodynamic generator, which ensures high thermoelectric conversion efficiency while avoiding the harsh working conditions and large safety hazards of existing methods.

A nuclear fission power plant (10) comprising: a first fluid circuit (130) to circulate gas; a nuclear reactor core (20) comprising: a fuel (20) and a moderator (30); the nuclear fission power plant further comprising a neutron reflector (60), one or more primary control rods (70), one or more secondary control rods (80), and a containment vessel (90) substantially surrounding the nuclear reactor core and allowing gas in the gas circuit to flow through both the containment vessel and the nuclear reactor core, and an open Brayton power system coupled to the first fluid circuit via a second fluid circuit (160), the open Brayton power system comprising: a compressor (210); a turbine system (220); and a generator system (230); the open Brayton power system being arranged such that the turbine system is configured to drive the compressor and the generator system.

A nuclear fission reactor system (10) which comprises a nuclear reactor unit (12) having a fuel block (400) with a central axis (402) extending along the length of the fuel block (400) between a first surface (412) and a second surface (422). The fuel block (400) defines a plurality of fuel assembly chambers (404) which extend from an inlet opening (410) on the first surface (412) of the fuel block (400) to an outlet opening (420) on a second surface (422) of the fuel block (400). There are also provided a plurality of fuel assemblies (100). Each fuel assembly (100) comprises a fuel compact (200) which defines a flow passage (202) running from a flow inlet (204) provided at a first end (206) of the fuel compact (200) to a flow outlet (208) provided at a second end (210) of the fuel compact (200), the passage (202) defining an internal surface (222) of the fuel compact (200). A displacer element (300) is provided in the coolant flow passage (202) and mounted such that a clearance (212) is maintained between the internal surface (222) of the fuel compact (200) and the displacer element (300) to define an annular coolant flow passage (230). Each of the plurality of fuel assemblies (100) is located in a respective one of the plurality of fuel assembly chambers (404). At least one of the fuel assemblies (100) of the plurality of fuel assemblies (100) is configured to transfer heat to the coolant in its annular coolant flow passage (230) at a first rate; and at least one other of the plurality of fuel assemblies (100) is operable / configured to transfer heat to the coolant in its annular coolant flow passage (230) at a second rate.

To provide a fast neutron detector capable of selectively detecting fast neutrons even under a high-temperature environment.SOLUTION: A fast neutron detector 50 according to an embodiment includes: a sealed container 11 having a tubular portion 11a, a first end portion 11b, and a second end portion 11c; a reaction portion 56 provided on an inner surface of the tubular portion 11a and containing a fast-fissionable nuclide; an internal gas 13 sealed in the sealed container 11 and ionized by nuclear fission fragments generated by a nuclear fission reaction of the fast-fissionable nuclide; a central conductor portion 15 accommodated in an internal space 11s of the sealed container 11, electrically insulated from the tubular portion 11a and extending in a longitudinal direction; and a high-temperature thermal neutron shielding portion 57 arranged to cover a radially outer side of the tubular portion 11a and containing a thermal neutron capturing nuclide. The high-temperature thermal neutron shielding portion 57 has a melting point higher than an environmental temperature at a position where the fast neutron detector 50 is installed.SELECTED DRAWING: Figure 1

The invention is suitable for the technical field of nuclear detection and embedded systems, and provides an embedded fission chamber assembly and a method for monitoring delayed neutrons thereof.The embedded fission chamber assembly comprises an outer cylinder, the outer cylinder serves as a shell structure of the assembly, a fission chamber body is arranged in the outer cylinder and fixedly installed in the outer cylinder, and the fission chamber body is arranged in the outer cylinder; and the fission chamber main body forms a basic framework of the detection core chamber. The fission chamber main body is internally provided with a gas filling chamber, and the gas filling chamber is used for filling working gas; a collecting electrode and a high-voltage electrode penetrating through the head and the tail are assembled on the collecting electrode in the gas filling chamber, the high-voltage electrode serves as an electric field applying end, and the collecting electrode serves as a signal output end; the outer wall of the collecting electrode and the inner wall of the high-voltage electrode are plated with high-concentration uranium 235 layers; the uranium plating layer serves as a fission material coating and directly participates in nuclear fission reaction caused by neutrons, a large number of fission fragments are generated, and ionization signals are remarkably enhanced. The design of the uranium plating layer can reduce the covering effect of the gamma-ray background on the neutron signal and improve the signal-to-noise ratio of the signal. Double electromagnetic shielding is achieved through the staggered design of the inner shielding layer and the outer shielding layer, external radiation interference and electromagnetic noise are restrained, and the signal distortion rate is reduced.

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.