34results about "Moderator/core" patented technology

Fuel bundle has plurality of twisted ribbon fuel rodlets in hexagonal packing or circle packing arrangement in a core region 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 void spaces in core region 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 a nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

The present application relates to a kind of nuclear reactor support mechanism, wherein nuclear reactor support mechanism includes several vertical support structures;Any vertical support structure includes lug, and lug type support is supported by lug;Lug includes base and at least one rib plate;One end of base is arranged in lug type support, and displacement can occur in lug type support along the length direction of base and / or the width direction of base;Nuclear reactor support mechanism further includes at least one first lateral support structure, and the first lateral support structure includes at least one first lateral support body, and the length direction of the first lateral support body is same with the radial direction of equipment, and one end of the first lateral support body can be connected on the circumferential side of equipment.The nuclear reactor support mechanism of the present application can be used on the equipment with high length-diameter ratio and vertical arrangement in the reactor, to ensure the release of cold and hot equipment self-expansion and pipe elongation, to ensure the verticality of equipment, and to facilitate the optimization of equipment stress, to improve the reliability of equipment.

In some embodiments, a power generation system may include a first nuclear reactor, which may include a vessel having a wall defining a cavity. The nuclear reactor may include a core disposed within said cavity. Said core may include a solid matrix material defining one or more channels. A fuel material may be disposed in said one or more channels. Said solid matrix material may be a primary heat transfer medium. The power generation system may include an electric generating system having a secondary heat transfer medium. The power generation system may include one or more heat exchangers thermally coupled to said vessel wall. Said primary heat transfer medium may transfer heat generated by the fuel material to the one or more heat exchangers. Said secondary heat transfer medium may draw heat from said one or more heat exchangers.

The invention relates to a method for constructing an underground nuclear installation on a site (10) comprising a shaft (12) bored into the ground (14, 16) and defining a bottom (12a), at a given depth relative to the ground surface, and an opening (12b, 12b1, 12b2) located at the level of the ground surface surrounding the shaft. The method comprises the following phases: - construction of a protective slab (D1, D2; D; 230) against external aggressions on an area (Zcd) of the ground surface, referred to as the slab construction area, located next to the opening (12b, 12b1, 12b2) of the shaft, - construction of a reactor building (B1, B2) inside the shaft (12), the phases of construction of the protective slab (D1, D2; D; 230) and the reactor building (B1, B2) being carried out in parallel. Figure for the abridged version: Fig. 3

The present invention provides a nuclear fission reactor structure and a method for manufacturing the same that comply with neutron engineering and thermal management requirements for nuclear fission reactors, while reducing manufacturing complexity and variability. [Solution] Multiple layers form a nuclear fission reactor structure. Each layer has an inner segment body, an intermediate segment body, and an outer segment body (each segment body is separated by a contact surface). The layer includes multiple cladding arms having an involute curve shape that radiates outward in a helical manner from the radially inner end to the radially outer end. The chambers of the involute curve cladding arms contain the fuel composition (and / or other materials such as moderators and interfering materials).

The invention relates to an advanced nuclear fuel channel design for fast-spectrum reactors, featuring an annular O-ring configuration that supports natural circulation of molten fuel. The channel's variable cross-section is optimized to enhance fission in the core zone and neutron capture in the breeding zone. Radial distribution ensures a compact arrangement in the core and wider spacing in the breeding zone for improved neutron management and criticality control. The design integrates optional collectors for circulation support and is compatible with liquid metal or high-temperature gas coolants. This system offers a high-efficiency solution for reactors requiring extended operation and in-situ breeding capabilities.

A thermal transfer unit may include one or more modules having a surface to volume ratio of greater than four hundred square meters per cubic meter. One or more of said modules may include a fluid inlet portion. Said fluid inlet portion may include a fluid inlet surface. One or more of said modules may include a thermal interface portion configured to interface with and thermally couple to an object for temperature regulation of the object. Said thermal interface portion may include a fluid return surface. Said module may include a matrix of pores configured to effect fluid flow. Said module may include a plurality of fluid return channels extending from said fluid return surface to an outlet. Said module may include a matrix of pores on or proximate said fluid inlet surface. Said module may include a matrix of pores on or proximate said fluid return surface.

The utility model belongs to the field of reactor, concretely relates to a kind of space reactor neutron source assembly and reactor system. Wherein space reactor neutron source assembly includes linear moving mechanism and the neutron source rod body of linear moving mechanism output end being arranged, the neutron source rod body includes neutron source functional area, gap and cladding sequentially arranged from inside to outside;The neutron source functional area includes sequentially arranged heat transfer zone, fuel area I, partition area I, neutron source, partition area II and shutdown area. The space reactor neutron source assembly provided by the utility model better utilizes the important position of reactor core center. It can move up and down on the core center, and the structure is simple and compact, efficiently realizes the functions of fuel auxiliary combustion, neutron source start-up, shutdown and reactivity adjustment.

Underground nuclear installation (10), comprising: - a vertical shaft (12) having, at a lower end, a bottom (12a) and, at an upper end, an opening (12b), - at least one reactor building (26) housed in the shaft, - at least one protective slab (20) against external aggressions which seals the opening (12b) of the shaft by extending in particular above said at least one reactor building, - at least one nuclear reactor containment (30) enclosed within said at least one reactor building (26) and supported by at least one support slab (32) resting on the bottom of the shaft by means of a plurality of seismic isolation devices (SIDs), - and / or at least one nuclear fuel storage pool (NFSP) housed in the shaft and supported by at least one support slab (DS) resting on the bottom of the shaft by means of a plurality of seismic isolation devices (SIDs). Figure for the summary: Fig. 3.

The application discloses a low-side-flow reflector module, a low-side-flow reflector, a core structure and a high-temperature gas cooled reactor. The low-side-flow reflector module comprises a module body and a flow guide block. A contact surface of the module body for contacting an adjacent low-side-flow reflector module comprises a profiled area and a planar area. When two adjacent low-side-flow reflector modules are assembled, a gap flow channel is formed, and a gap flow energy dissipation area is formed in the profiled area. The flow guide block is arranged in the gap flow energy dissipation area, and separates the gap flow channel in the gap flow energy dissipation area into a first gap flow channel and a second gap flow channel. When the gap flow enters the gap flow energy dissipation area, the flow is divided into a first gap sub-flow and a second gap sub-flow by the flow guide block. The first gap sub-flow forms a reverse flow after passing through the first gap flow channel. The direction of the reverse flow is opposite to that of the second gap sub-flow. The application can increase energy loss in flow, thereby increasing flow resistance and achieving the purpose of reducing side flow.

A thermal transfer unit may include one or more modules. One or more of said modules may include a fluid inlet portion, said fluid inlet portion may include a fluid inlet surface. One or more of said modules may include a thermal interface portion configured to interface with and thermally couple to an object for temperature regulation of the object. Said thermal interface portion may include a fluid return surface. Said module may define a plurality of micro-channels. Said module may define a plurality of fluid return channels extending from said fluid return surface to an outlet. Said module may define a plurality of lateral fluid supply channels on said fluid inlet surface interconnecting at least a subset of said micro-channels. Said module may define a plurality of lateral fluid return channels on said fluid return surface interconnecting at least a subset of said micro-channels and said fluid return channels.

A nuclear reactor may include a vessel having a wall defining an interior cavity. The nuclear reactor may include a spherical core disposed within the cavity. The spherical core may include a plurality of fuel elements. Each fuel element may extend from an outer periphery of the core along a radius to a central portion of the core. Each fuel element may include a solid matrix material that defines a plurality of fuel channels. The core may include a fuel material disposed in the plurality of fuel channels. The core may include one or more control rod channels, each extending from the outer periphery of the core along a radius to the central portion of the core. The nuclear reactor may include a reactivity control system that may have one or more control rods comprising a neutron absorbing material for insertion into the one or more control rod channels.

This invention discloses a boron-containing carbon reactor internal component for high-temperature gas-cooled reactors and its preparation method, belonging to the technical field of carbon reactor internal components. The boron-containing carbon reactor internal component for high-temperature gas-cooled reactors is prepared by uniformly dispersing boron carbide in phenolic resin to obtain a boron-containing phenolic resin binder, which is then added to calcined coke, mixed countercurrently, molded, and calcined at a controlled temperature. The boron-containing carbon reactor internal component for high-temperature gas-cooled reactors prepared by this invention has high strength, dense and uniform blank, and outstanding comprehensive mechanical properties. This invention is applicable to the preparation of boron-containing carbon reactor internal components for high-temperature gas-cooled reactors.

Fuel bundle has plurality of twisted ribbon fuel rodlets in hexagonal packing or circle packing arrangement in a core region 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 void spaces in core region 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 a nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

A fixed related assembly of a nuclear reactor core, comprising functional rods (1) for being inserted into guide tubes of a fuel assembly (3) to achieve different functions, and a pressing system (2) for fixing and connecting the functional rods (1). The pressing system (2) comprises a central cylinder (21) having an inner cavity, and a supporting plate (22); the supporting plate (22) is fixedly connected to the central cylinder (21); the inner cavity of the central cylinder (21) comprises a first cavity (211). The pressing system (2) further comprises a pressing structure (23); the pressing structure (23) comprises a pressing rod (231), a pressing spring (232), and a spring seat (233); the pressing spring (232) fills the first cavity (211); one end of the spring seat (233) penetrates into the first cavity (211) and abuts against the lower end of the pressing spring (232), and the other end of the spring seat (233) is used for pressing against an upper tube seat of the fuel assembly (3); the pressing rod (231) is fixedly connected to the central cylinder (21), and is located at the side of the supporting plate (22) away from the spring seat (233); the pressing rod (231) is used for abutting against the side of a reactor core upper plate (4) of a nuclear reactor core close to the fuel assembly (3), so as to prevent a related assembly from axially moving.

Fuel bundle has plurality of twisted ribbon fuel rodlets in hexagonal packing or circle packing arrangement in a core region 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 void spaces in core region 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 a nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

A portable nuclear power system includes a nuclear reactor. The nuclear reactor includes a core comprising a vessel housing a nuclear fuel that produces radiation, a sleeve of a high temperature moderator material disposed circumferentially about the core, and a neutron screen disposed circumferentially about the sleeve. The portable nuclear power system generates electricity using heat received from the nuclear reactor and has one or more cooling units in thermal communication with the electricity generating unit.

An anti-proliferation technique is disclosed to reduce the likelihood of nuclear proliferation due to the use fissionable fuel salts. The technique includes doping the fuel salt with one or more elements (referred to herein as activation dopants) that, upon exposure to neutrons such as would occur in the fuel salt when a reactor is in operation, undergo a nuclear reaction to, directly or indirectly, form highly active “protecting isotopes” (of the same element as the activation dopant or a different element). A sufficient mass of activation dopants is used so that the Figure of Merit (FOM) of the fuel salt is decreased to below 1.0 within some target number of days of fission. This allows the FOM of the fuel salt to be controlled so that the fuel becomes too dangerous to handle before to the creation of a significant amount of weaponizable isotopes.

The application discloses a reactor upper in-core component emergency back-to-pile support device and method, relates to the technical field of maintenance operation of pressurized water reactor nuclear power plants, and aims to solve the problem that the upper in-core component cannot be directly hoisted back to the core when the underwater component of the fuel transfer system fails during the unloading or loading process of the existing device. The device comprises a temporary support ring as the main body of the device, the temporary support ring is an integral ring structure, a plurality of uniformly distributed circular through holes are formed in the temporary support ring, a plurality of positioning grooves and a plurality of lifting lug holes are arranged at the outer edge of the temporary support ring, a plurality of spin lock grooves are formed in the upper surface of the temporary support ring, and a guide sleeve is detachably connected to the temporary support ring. The device can hoist the upper in-core component back to the core in the case that the underwater component of the fuel transfer system fails during the unloading or loading process, and the upper in-core component is raised on the temporary support ring, so that the low-span of the refueling pool can be independently drained, and the maintenance of the underwater component of the fuel transfer system on the reactor plant side can be implemented.

The application relates to a high-temperature-resistant composite neutron moderator material and a manufacturing method thereof, and belongs to the nuclear power field. The manufacturing method of the high-temperature-resistant composite neutron moderator material comprises the following steps: determining the hydrogen partial pressure of a metal hydride at a working temperature, establishing a moderator material particle model comprising a metal hydride core, a buffer layer and a SiC sealing layer and calculating the stress borne by the SiC sealing layer at the working temperature; calculating the allowable stress of the SiC sealing layer at the working temperature and adjusting the moderator material particle model according to the allowable stress to obtain a corrected moderator material particle model; and manufacturing a high-temperature-resistant composite neutron moderator material finished product based on the corrected moderator material particle model. The method can be used for manufacturing a neutron moderator material with good stability and reliability at a high temperature, and improves the safety and reliability of a commercial nuclear power plant reactor.

Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a heat pipe network having an evaporator region, an adiabatic region, and a condenser region. The heat pipe network can define a plurality of flow paths having an increasing cross-sectional flow area in a direction from the evaporator region toward the condenser region. The system can further include nuclear fuel thermally coupled to at least a portion of the evaporator region. The heat pipe network is positioned to transfer heat received from the fuel at the evaporator region, to the condenser region. The system can further include one or more heat exchangers thermally coupled to the evaporator region for transporting the heat out of the system for use in one or more processes, such as generating electricity.

The application discloses a heat pipe cooled molten salt reactor core, which comprises a fuel assembly, a moderator, an active zone cladding, a reflector, a core shell and a control drum; the active zone cladding, the reflector and the core shell are sequentially arranged from inside to outside, the fuel assembly is inserted into the active zone cladding, the fuel assembly comprises an inner tube and an outer tube sleeved outside the inner tube, an annular gap is formed between the outer wall of the inner tube and the inner wall of the outer tube, and the annular gap or the inner tube is filled with fuel salt. The heat pipe cooled molten salt reactor core can provide support for realizing compact and small design of the heat pipe cooled molten salt reactor, can reduce the fissile nuclear fuel loading required by criticality, and effectively improves the inherent safety and economy of the reactor.

A nuclear fuel, moderator, and absorber (FMA) assembly provides a mechanism to tailor the fissile material density, moderating power, and neutron absorbing functions at each lateral and axial location within the core; maintains the geometry of the materials required for these functions; retains gaseous fission products, solid fission products, and gaseous phases such as hydrogen as necessary. The FMA concept may be used in many different types of reactors to optimize reactor fuel utilization and safety performance. Advanced methods such as genetic algorithms or other methods that are currently available or become available and the use of artificial intelligence may be used to specify the components, materials, or features of each individual FMA for optimization of reactor core loading that results in superior reactor safety and economic performance. The Fuel Moderator and Absorber (FMA) assembly may be configured to enhance the retention of fission products, allowing siting of nuclear reactors with a minimal Emergency Planning Zone.

A reactor body structure and a reactor system. The reactor body structure (100) comprises: a reactor pressure vessel (1), the reactor pressure vessel (1) comprising a bottom closure head (3), and the

The invention relates to a method for constructing a buried nuclear facility at a site (10), comprising a well (12) excavated into the ground (14, 16) and defining a bottom (12a) at a given depth relative to the ground surface, and an opening (12b, 12b1, 12b2) located at the ground surface surrounding the well. The method comprises the following phases: - constructing a protective slab (D1, D2; D; 230) for protection against external threats over an area (Zcd) of the ground surface, referred to as the slab construction area, located adjacent to the opening (12b, 12b1, 12b2) of the well; - constructing a reactor building (B1, B2) inside the well (12), wherein the construction phases of the protective slab (D1, D2; D; 230) and the reactor building (B1, B2) are carried out in parallel.

A fuel element with an ordered particle fuel particle packing to improve lifetime and retention. The fuel element includes an encapsulation matrix and a plurality of coolant channels formed in the encapsulation matrix. Fuel element further includes a plurality of fuel particle matrices disposed within the encapsulation matrix. Each of the fuel particle matrices is ordered in a vertically aligned geometry or a twisted geometry to: (a) substantially laterally surround a contour of a respective coolant channel, and (b) orient substantially longitudinally or substantially helically along the respective coolant channel. For example, each of the fuel particle matrices can include a plurality of fuel particles that are a cluster around the respective coolant channel. The encapsulation matrix can be a high-temperature matrix. A fabrication method for the fuel element includes three-dimensional printing the fuel element and placing the plurality of fuel particles in selected locations in the fuel element.

The invention relates to the technical field of reactor structures, in particular to a hanging basket assembly, reactor internals and a reactor based on reactor core sinking arrangement and direct safety injection. The reactor comprises a force vessel and a pressure vessel, wherein the force vessel comprises a pressure cylinder, a pressure vessel top cover and a supporting key; a pressure vessel inlet connecting pipe, a pressure vessel outlet connecting pipe and a safety injection connecting pipe are welded on the pressure vessel cylinder, the pressure vessel inlet connecting pipe is higher than the pressure vessel outlet connecting pipe, and the safety injection connecting pipe is positioned below the pressure vessel outlet connecting pipe; and the supporting key is welded at the lower end of the inner wall of the pressure vessel cylinder body and is matched with the supporting key groove at the bottom of the reactor core supporting plate, so that the reactor internals are limited in the radial direction and the axial direction. The device is simple in structure, easy to process and manufacture and high in safety performance.