20 results about "Fission reactor" patented technology

Techniques are described for producing actinium-225 by arranging a converter material at least partially around a target material, where the target material includes radium-226. The converter material comprises a compound of lithium and hydrogen at least partially enriched with lithium-6 and deuterium, and is configured to convert thermal neutrons to fast neutrons, which are then incident on the radium-226. If the fast neutrons have a kinetic energy of at least 6.4 MeV, they will initiate a (n,2n) reaction that converts radium-226 into radium-225, which then decays into actinium-225. The process can desirably be performed within an environment rich in thermal neutrons, such as within a fission reactor.

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.

The invention relates to the technical field of neutron measurement, and particularly discloses a thermoluminescence field dosimeter for measuring neutron energy spectrum.The thermoluminescence field dosimeter comprises a thermoluminescence field dosimeter body, and the thermoluminescence field dosimeter body comprises a front-end assembly, a rear-end assembly and a center assembly located between the front-end assembly and the rear-end assembly; the center assembly and the rear end assembly are detachably connected with the front end assembly. Wherein the distance between the front surface of the central assembly and the front surface of the front end assembly is 1mm, the distance between the front surface of the rear end assembly and the front surface of the front end assembly is 7mm, and the front surface of the central assembly and the front surface of the rear end assembly are respectively provided with a 6LiF thermoluminescence dosage piece and a 7LiF thermoluminescence dosage piece. The thermoluminescence field dosimeter is wide in neutron energy response range, covers 0.0253 eV-20 MeV, can be suitable for neutron energy spectrum measurement of nuclear facilities such as fission reactors, fusion reactors and medical accelerators, and is particularly suitable for measurement in measurement occasions with narrow spaces and large neutron field gradients.

The application relates to the technical field of nuclear power engineering equipment, in particular to a composite-resistant repair robot applied to a fissile reactor special box chamber environment; the composite-resistant repair robot comprises a crawler trolley, a composite mechanical arm, the composite mechanical arm comprises a three-axis arm and a six-axis arm, one end of the three-axis arm is connected with the crawler trolley, and the other end is connected with the six-axis arm, and a manipulator, the manipulator is fixed at the tail end of the six-axis arm and is used for performing repair work in the fissile reactor special box chamber; the fissile reactor special box chamber composite-resistant repair robot has the advantages that through the unique design and the innovative technical scheme, the safety, the efficiency, the stability and the practicability of repair work on a process pipeline in an extreme environment are remarkably improved, and the fissile reactor special box chamber composite-resistant repair robot has important application value and social significance.

The inventors have developed technology to improve the generation of daughter isotopes for clinical treatments. The technology includes systems and methods for using a liquid target to deliver parent isotopes to a reactor for neutron bombardment and subsequently separating desired daughter isotopes from the liquid target. According to an aspect of the technology described herein, a method of obtaining desired daughter isotopes comprises pumping a liquid target solution comprising a parent isotope through a fluid path that includes a first portion that passes through a fission reactor, a second portion that passes through a pump, and a third portion that passes through an isotope capture device.

Heat pipe fuel element includes an evaporation section, a condensing section, a capillary section connecting the evaporation section to the condensing section, and a primary coolant. In a cross-section in a plane perpendicular to a longitudinal axis of the evaporation section, the heat pipe fuel element includes a cladding layer enclosing an interior area including a fuel body formed of a fissionable fuel composition and that has an outer surface oriented toward the cladding layer and an inner surface defining a periphery of a vaporization space of the evaporation section. The fuel body has a structure with a shape corresponding to a mathematically-based periodic solid, such as a triply periodic minimal surface (TPMS), and the evaporation sections of a plurality of heat pipe fuel elements are arranged in a phyllotaxis pattern (as seen in a cross-section in a plane perpendicular to a longitudinal axis of the active core region).

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

The fission reactor has a shell surrounding a reactor space that is a central longitudinal channel, and a plurality of axially extending rings having adjacent rings form an annular cylindrical space in which a plurality of primary axial tubes are located circumferentially. The circumferentially adjacent primary axial tubes are separated by one of a plurality of secondary channels, and a plurality of webbings connect at least a portion of the plurality of primary axial tubes to an adjacent structure. The fissile fuel composition is located in at least a portion of the plurality of secondary channels, and the primary coolant passes through at least a portion of the primary axial tubes. Addition and / or subtraction manufacturing techniques form an integral and single structure for the fuel-loaded reactor space. During manufacturing and construction, the reactor design can be analyzed using a computational platform that integrates and analyzes data from on-site monitoring during manufacturing.

The inventors have developed technology to improve the generation of daughter isotopes for clinical treatments. The technology includes systems and methods for using a liquid target to deliver parent isotopes to a reactor for neutron bombardment and subsequently separating desired daughter isotopes from the liquid target. According to an aspect of the technology described herein, a method of obtaining desired daughter isotopes comprises pumping a liquid target solution comprising a parent isotope through a fluid path that includes a first portion that passes through a fission reactor, a second portion that passes through a pump, and a third portion that passes through an isotope capture device.

The invention relates to the technical field of alloy materials, and provides a FeCrV-series low-activation high-strength high-entropy alloy and a preparation method and application thereof. The general formula of the alloy is represented by FeCrVTaxWyTiz, wherein 0 lt; x is less than or equal to 0.2, 0lt; y < = 0.2, 0 < = z < = 0.4. The room-temperature mechanical property of the high-entropy alloy is emphatically optimized, the yield strength of the designed alloy at the room temperature is higher than 1370 MPa, and the plastic deformation exceeds 3.3%. Compared with an existing low-activation high-entropy alloy, the low-activation high-entropy alloy has the advantages of being excellent in comprehensive performance and low in cost. The material can be used as a nuclear material of a fusion reactor and a new generation fission reactor, solves the problems of high cost, insufficient mechanical properties and the like of a traditional low-activation nuclear material, and further promotes the application and development of nuclear energy in the fields of aviation, national defense and the like.

The application discloses a boron-containing stainless steel with high shielding performance and a preparation method thereof, relates to the field of fusion reactor irradiation shielding materials, and can also be applied to other fields requiring shielding of neutrons and gamma rays, such as fission reactors, nuclear power devices, nuclear waste storage racks and the like. The boron steel contains the following components in percentage by weight: Cr 7.5-25%, Ni 8.5-18.5%, Mn 0.5-4.3%, B 1.8-4.5%, C 0.02%-0.06%, and the balance is Fe and inevitable impurities. The components of the alloy are proportioned according to the application, atomized, mixed, sintered and machined, and finally, a block boron steel with high boron content, high density, uniform boride distribution and good shielding performance is obtained. The high-performance boron steel shielding material improves the shielding efficiency of thermal neutrons, and provides support for the development of DEMO reactors, compact fusion reactors and other shielding fields.

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.

Techniques are described for producing actinium-225 by arranging a converter material at least partially around a target material, where the target material includes radium-226. The converter material comprises a compound of lithium and hydrogen at least partially enriched with lithium-6 and deuterium, and is configured to convert thermal neutrons to fast neutrons, which are then incident on the radium-226. If the fast neutrons have a kinetic energy of at least 6.4MeV, they will initiate a (n,2n) reaction that converts radium-226 into radium -225, which then decays into actinium-225. The process can desirably be performed within an environment rich in thermal neutrons, such as within a fission reactor.

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 inventors have developed technology to improve the generation of daughter isotopes for clinical treatments. The technology includes systems and methods for using a liquid target to deliver parent isotopes to a reactor for neutron bombardment and subsequently separating desired daughter isotopes from the liquid target. According to an aspect of the technology described herein, a method of obtaining desired daughter isotopes comprises pumping a liquid target solution comprising a parent isotope through a fluid path that includes a first portion that passes through a fission reactor, a second portion that passes through a pump, and a third portion that passes through an isotope capture device.

Fuel bundle has plurality of twisted ribbon fuel rodlets arranged in hexagonal packing or circle packing arrangement in a reactor core encased in a multilayer casing. Arrangement of twisted ribbon fuel rodlets is facilitated by rodlet seating fixture with seating surface having a plurality of protrusions that form a receiving space for ends of the twisted ribbon fuel rodlets. Manufacture of the fuel bundle incorporates fiber manufacturing technologies and, optionally, infiltration of spaces in the reactor core by infiltrant. Twisted ribbon fuel rodlet manufacturing system has sub-systems that impart twist periodicity to extruded ribbons, inspect twisted extruded ribbons, and cut twisted extruded ribbons to length. Inspection sorts twisted ribbon fuel rodlets as well as provides feedback to adjust operation of sub-systems. The fuel bundle (and optional fuel bundle support) can be incorporated into a fuel assembly of nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

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).

A nuclear fission reactor comprising a passive thermal shut-down device, and a reactor core containing fissile fuel. The passive thermal shutdown device comprises a reservoir and a Pythagorean syphon. The reservoir is in thermal communication with the reactor core, and containing a neutron poison material which has a free surface. The Pythagorean syphon has an inlet within the reservoir, an outlet in fluid communication with the reactor core. When the neutron poison material overtops the syphon due to thermal expansion, the neutron poison material flows through the Pythagorean syphon and into the reactor core. Also provided are nuclear fission reactors having passive thermal shutdown devices using a Pythagorean syphon to control the flow of fissile fuel, neutron moderators, or neutron reflectors.

An insulated fuel assembly core comprises multiple fuel monoliths, an exhaust support plate, an exhaust shield assembly, and an insulating layer, wherein the multiple fuel monoliths are axially positioned along the longitudinal axis, and each of the multiple fuel monoliths has an eccentric cylindrical shape and a composition containing fissile fuel components. Channels in the exhaust support plate are oriented so that the propellant gas flow through the exhaust support plate does not collide with the exhaust shield assembly. The insulated fuel assembly core is manufactured by forming a tensioned fuel monolith stack mandrel assembly using mandrel spacers and internal tension-imparting components, and by forming an insulating layer on the outer surface of the tensioned fuel monolith stack mandrel assembly by mandrel winding. The insulated fuel assembly core can be incorporated, for example, into the fuel assembly of a nuclear propulsion fission reactor structure of a nuclear thermal propulsion engine.