36 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 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.

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.

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 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 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

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.

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.

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.

A defective fuel bundle positioning system for a heavy water moderated nuclear fission reactor having a refueling machine, the system including a test tool defining an interior volume, the test tool configured to be received in a corresponding fuel channel of the refueling machine and the reactor; and a test container defining an interior volume, wherein the test container is configured to be received in the interior volume of the test tool and, when the test tool is disposed in the corresponding fuel channel of the reactor, the interior volume of the test container is configured to receive primary fluid from the reactor.

The present application relates to a kind of NAD (P) H response type diagnosis and treatment integrated boron medicine and its preparation method, the boron medicine with 10 B acetylacetone difluoroboric ester as mother nucleus, by introducing the cell nucleus target ability of N-containing or S-containing heterocyclic structure, simultaneously introduce the response unit that can specifically respond to high expression NAD (P) H in tumor microenvironment, activate fluorescence / photoacoustic dual-mode imaging signal, realize the visual positioning of tumor site.On this basis, the present application realizes three big core functions: one is through NAD (P) H response point light imaging, effectively reduce background signal interference;Two is by means of N or S atom and the combination of cell nucleus DNA / RNA, will 10 B be accurately delivered to nucleus, significantly improve BNCT killing efficiency;Three is under the guidance of imaging, thermal neutron irradiation is carried out, triggers 10 B (n, α) 7 Li nuclear fission reaction, finally realizes high-precision diagnosis and treatment integration.The preparation method of the boron medicine is also disclosed, can be used for preparing malignant tumor diagnosis and treatment drug, has good clinical application prospect.

A nuclear reactor unit (200) for a nuclear fission reactor system (100) comprising a fuel assembly (400). The fuel assembly (400) comprises a tube (402), a sleeve member (430) and a support member (800). An insulation gap (604) is maintained between the tube (402) and the sleeve member (430). The support member (800) defines an insulator fluid supply passage (812) which is in fluid communication with the insulation gap (604) and a source of insulator fluid (610). A first seal (822) is provided between the sleeve member (430) and the support member (800) in a location passage (806) in the support member (800). The first seal (822) is provided between a second side (804) of the support member (800) and the insulator fluid supply passage (812) along the location passage (806).

A fuel assembly 400 for a nuclear fission reactor system comprises a pressure tube 402 and a single sleeve member 430 provided inside the pressure tube. The sleeve member 430 defines a chamber 434 whi

The present invention relates to a nuclear-propulsion ship with improved stability, comprising: a reactor disposed within the hull that generates steam using thermal energy generated during nuclear fission; a turbine disposed within the hull and connected to the reactor that rotates due to impulse and reaction forces generated when the turbine collides with the steam; and a gyro stabilizer disposed within the hull that suppresses tilt of the hull through precession of a rotor that rotates around a spin axis, a gimbal that rotatably supports the spin axis, and a frame that rotatably supports the gimbal, wherein the turbine is attached to the spin axis of the gyro stabilizer and transmits rotational force to the spin axis, and the gyro stabilizer includes a generator attached to the spin axis, and the turbine rotates the spin axis and rotor, activating the generator to produce electricity.

A nuclear fission reactor system (10) comprising a reactor unit (12) having a fuel block (400) having a central axis (402) extending along a 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) extending from an inlet opening (410) on the first surface (412) of the fuel block (400) to an outlet opening (420) on the second surface (422) of the fuel block (400). A plurality of fuel assemblies (100) are also provided. Each fuel assembly (100) includes a fuel compact (200) defining a passage (202) extending from an inlet (204) at a first end (206) of the fuel compact (200) to an outlet (208) at a second end (210) of the fuel compact (200), the passage (202) defining an inner surface (222) of the fuel compact (200). A displacer element (300) is disposed within the cooling passage (202) and is mounted such that a clearance (212) is maintained between the inner surface (222) of the fuel compact (200) and the displacer element (300) to define an annular cooling passage (230). Each of the plurality of fuel assemblies (100) is positioned 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 cooling channel (230) at a first rate, and at least one other fuel assembly of the plurality of fuel assemblies (100) is operable / configured to transfer heat to the coolant in its annular cooling channel (230) at a second rate.

The invention discloses a fission reactor adopting a lithium lead alloy as a coolant, and belongs to the field of nuclear fission reactors. Aiming at the problems of high radiotoxicity of polonium-210 in the existing lead-bismuth cooled reactor and difficulty in engineering realization caused by overhigh melting point of a pure lead cooled reactor, the invention provides a fission reactor scheme taking a lithium-lead alloy as a coolant, and the fission reactor scheme has the following advantages: 1, the generation of polonium-210 is fundamentally eliminated, and the radioactivity safety performance is improved; 2, the melting point of the lithium-lead alloy is lower than that of pure lead, and engineering implementation is more feasible; the invention provides an innovative solution for solving the contradiction between the safety and the engineering feasibility of the current lead bismuth or pure lead cooling reactor, and has important engineering application value.

[Problem] To provide: a high-temperature gas-cooled reactor fuel capable of immobilizing radioactive cesium, which is produced by nuclear fission in fuel kernels of a high-temperature gas-cooled reactor and released from coated fuel particles, within the high-temperature gas-cooled reactor fuel in a temperature range of room temperature to 1600°C; and a raw material powder to be used for the high-temperature gas-cooled reactor fuel. [Solution] A high-temperature gas-cooled reactor fuel having the function of chemically trapping radioactive cesium comprises: coated fuel particles 6 each including at least a fuel kernel 1 containing a fissile material, a low-density pyrolytic carbon layer 2 coating the fuel kernel 1, and an outer high-density pyrolytic carbon layer 5 coating the low-density pyrolytic carbon layer 2; and a matrix material 7 configured to retain the coated fuel particles 6 and composed of carbon or silicon carbide. Aluminum silicate is added to a raw material powder of the matrix material 7 and / or to a surface of the matrix base material 7.

The result is the controllable giant heavy hammer pressurization intermittent direct explosion type nuclear fusion steam power generation system. The invention belongs to the technical field of nuclear fusion power generation. The current nuclear fusion breakthrough direction is controllable nuclear fusion of magnetic confinement or inertial confinement, but the process is difficult. The rigorous technical difficulties of controllable nuclear fusion are avoided, controllable fusion is not pursued, and only result-controllable nuclear fusion is pursued. The method comprises the following steps of: sealing a fusion material with proper equivalent weight in the center of a giant steel disc column, instantaneously increasing the environmental pressure of the nuclear fusion material to tens of thousands of barometric pressures by utilizing potential energy and momentum of a giant steel heavy hammer, and increasing the pressure and the temperature by thousands of times again through auxiliary measures of electric heating, explosive explosion and nuclear fission, so as to realize nuclear fusion. As the equivalent weight of the fusion material is limited in advance, the fusion explosion can be safely sealed in the giant steel disc column. After fusion, the circulating water directly contacts with the steel disc column for heat exchange to generate steam, so that safe power generation is realized.

The present invention relates to a method for the synthesis of actinide chloride(s) from actinide oxide(s) present in a molten salt, the method using an aluminium(I) salt, a silicon(II) salt and / or a beryllium(III) salt, and optionally at least one chloride salt of an alkali and / or alkaline-earth metal. The present invention also relates to the use of an aluminium(I) salt, a silicon(II) salt and / or a beryllium(III) salt, for example aluminium chloride AlCl3, for the synthesis of actinide chloride(s) from actinide oxide(s) in a molten fuel salt for molten salt nuclear fission reactors (MSR).

The invention discloses a beryllium-oxide-based nuclear fuel element and a preparation method thereof.The beryllium-oxide-based nuclear fuel element comprises a fuel zone, the fuel zone comprises nuclear fuel dressing particles and a beryllium-oxide matrix, the beryllium-oxide matrix wraps the nuclear fuel dressing particles, the nuclear fuel dressing particles comprise nuclear fuel coating particles and beryllium-oxide layers, and the beryllium-oxide coating particles are coated with the beryllium-oxide matrix. The beryllium oxide layer wraps the nuclear fuel coated particles; and the fuel-free area wraps the fuel area. The fuel-free area is arranged on the surface of the fuel area, so that the problem that fuel particles in a nuclear fuel element without the fuel-free area are exposed and are damaged by external force is solved, the service stability and reliability of the beryllium oxide-based nuclear fuel element are improved, and the safety of a small modular reactor is improved. Meanwhile, beryllium oxide also has relatively high moderation capability and thermal conductivity, fast neutrons generated by nuclear fission can be moderated in time, and heat is efficiently transferred to the coolant.

The invention relates to the technical field of nuclear reactors, in particular to a neutron energy spectrum one-way regulation and control device and a lead-based fast neutron high-flux research reactor, and the regulation and control device comprises a first structure layer which comprises at least two neutron moderation elements, and a cylindrical irradiation cavity defined by the multiple neutron moderation elements is used for accommodating an irradiation target; the second structural layer comprises at least two first adaptive elements, and the multiple first adaptive elements can form a first cylindrical structure on the periphery of the first structural layer; the third structural layer comprises at least two second adaptive elements, and the multiple second adaptive elements can form a second cylindrical structure on the periphery of the second structural layer; wherein the plurality of first adaptive elements and the plurality of second adaptive elements are loaded with at least one of a low-energy thermal neutron absorbing material and a high-energy fast neutron strengthening material, and the energy of high-energy fast neutrons generated by nuclear fission of the reactor core can be reduced to a specific energy interval. The research stack is loaded with the regulation and control device.

A passive thermal shutdown device 403 for a nuclear fission reactor comprises a reservoir (101, Fig. 1) and a Pythagorean siphon. The reservoir is in thermal communication with the reactor core 404 an

A reactor that is operable to produce an isotope includes a region for containing a controlled nuclear fission reaction, the region segmented into a plurality of independent compartments, each of the compartments for containing a parent material in an aqueous solution that interacts with neutrons to produce the isotope via a fission reaction. Also provided are methods of producing an isotope using the same.

A nuclear fission reactor system (100) provided with a nuclear reactor unit (200). The nuclear reactor unit (200) may comprise a moderator fluid tank (202) for containment of a moderator fluid (204). The moderator fluid tank (202) may comprise a moderator tank fluid flow inlet (210) and a moderator fluid tank fluid flow outlet (212). The nuclear fission reactor system (100) may comprise a moderator fluid temperature control system (220) operable to control the temperature of the moderator fluid (204) at the moderator tank fluid flow inlet (210).