50 results about "Neutron reflector" patented technology

The invention relates to a nuclear reactor (1) having solid fuel assemblies (2) that are sealed and cooled individually in nominal operation by heat pipes (23). The invention substantially consists of a nuclear reactor (1) that operates in the fast neutron spectrum and is cooled by an array of one or more heat pipes (23). At least part of the evaporator (231) of one or more heat pipe(s) (23) is held and partially housed with one or more rods (22) of solid fuel pellets which are enclosed in a sheath in a sealed assembly which is partially filled with a liquid metal bath (21), which can be defined as a thermal seal between the rod sheaths and the heat pipes (23). The core (11) of the reactor (1) consists of an array of these sealed assemblies (2) (fuel rod(s) and heat pipe(s) immersed in a liquid metal bath) arranged within a tank (10) surrounded by a neutron reflector (12).

The invention relates to the technical field of power generation devices, and provides a nuclear fuel built-in loop free piston thermo-acoustic generator which comprises a thermo-acoustic engine, a control drum, a neutron reflecting layer and a piston type generator, the thermo-acoustic engine comprises a low-temperature heat exchanger, a heat regenerator and a reactor core which are arranged in sequence, and the reactor core is provided with a channel for working medium gas to circulate; the control drum is arranged on the peripheral side of the thermoacoustic engine; the thermoacoustic engine and the control drum are both arranged in the neutron reflecting layer, the piston type generator is provided with a main piston air cylinder, the main piston air cylinder is in acoustic communication with the outlet end of the thermoacoustic engine through an expansion cavity side resonance tube, and the piston type generator is used for converting part of acoustic power into electric energy and adjusting the acoustic impedance phase angle. The reactor core is directly used as a heat source to be arranged in the thermoacoustic engine, so that the reactor core directly replaces a hot end heat exchanger in the traditional technology, the arrangement of a middle heat transfer structure is avoided, the structure is simple, and the problem of low heat transfer efficiency caused by the heat transfer structure is avoided.

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.

A nuclear reactor core (1) for a molten salt nuclear reactor (100). The nuclear reactor core (1) has a tubular cylindrical center moderator vessel (10) for passage of a liquid moderator (11), a cylindrical fuel salt jacket surrounding the center moderator vessel (10), and a cylindrical neutron reflector jacket surrounding the cylindrical fuel salt jacket, wherein the cylindrical center moderator and neutron reflector vessel (10) has a largest inner cross-sectional area medially between a liquid moderator and neutron reflector inlet (12) of the center moderator and neutron reflector vessel (10) and a liquid moderator and neutron reflector outlet (13) of the moderator and neutron reflector vessel (10).

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.

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 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.

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.

The present invention provides a moderator and collimator for thermal neutron imaging, capable of providing high-flux, well-directional thermal neutrons for neutron imaging equipment such as mobile neutron radiography systems and neutron therapy devices. The moderator and collimator comprises a uniform moderator, a hole array moderator, and a hole array collimator, which are sequentially connected in a first direction; and a neutron reflector surrounding the uniform moderator, the hole array moderator, and the hole array collimator. The uniform moderator comprises at least one neutron moderating material. The hole array moderator comprises a plurality of first holes extending in a two-dimensionally closely spaced arrangement along the first direction, the hole array moderator having hole walls made of neutron moderating material. The hole array collimator comprises a plurality of second holes extending in a two-dimensionally closely spaced arrangement along the first direction, the hole array collimator having hole walls made of neutron absorbing material. The neutron reflector extends in the first direction and is attached to and wrapped around the uniform moderator, the hole array moderator, and the hole array collimator. The neutron reflector comprises at least one neutron reflecting material.

The application discloses a kind of partition arrangement's graphite-based dispersion fuel heat pipe reactor core structure, and low enrichment uranium fuel area center is equipped with the guide hole of adaptation emergency stop rod insertion, low enrichment uranium fuel area outside is successively coated high enrichment uranium fuel area, intermediate enrichment uranium fuel area, neutron reflector, inner shell, shielding layer and outer shell;Three uranium fuel areas are uniformly distributed with multiple heat pipe guide holes suitable for inserting heat pipe;Neutron reflector is uniformly distributed with multiple circular rotating holes suitable for rotating reactivity control drum in it in the middle, and the entire lateral wall of reactivity control drum is provided with arc length 120 degrees and cross section in the form of crescent-shaped neutron absorbing material layer along its circumference, which together with the cross section of reactivity control drum forms a circle;It can effectively flatten the core power, significantly improve the reliability and system economy of nuclear reactor operation;And all-solid-state core is more conducive to transportation, expands the application range;It can be used for power generation, and can also provide high-temperature process heat, with multi-purpose characteristics.

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 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.

Disclosed herein is a nuclear reactor system comprising a vessel encompassing a reactor core. An external loop line is connected to top and bottom portions of the vessel. A pump can circulate molten fuel through the reactor core and the external loop line. An external neutron reflector encompasses the vessel. External heaters heat the loop line and the reflector. The loop line, the reactor, or both, may be covered with insulation.

A nuclear reactor with sealed, individually cooled solid fuel assemblies operating nominally via heat pipes. The invention essentially consists of a nuclear reactor operating in the fast neutron spectrum, cooled by a network of one or more heat pipes. At least a portion of the evaporator of one or more heat pipes is partially housed with one or more solid fuel pellets confined in a cladding within a sealed assembly partially filled with a liquid metal bath, which can be described as a thermal seal between the fuel rod cladding and the heat pipes. The reactor core consists of a network of these sealed assemblies (fuel rod(s) and heat pipe(s) immersed in a liquid metal bath), arranged within a vessel surrounded by a neutron reflector. Figure for the abstract: Fig. 1

A nuclear fission power plant (10) comprising: a gas-cooled moderated nuclear reactor core (20) comprising: a fuel system (30); a moderator (35); and at least one core inlet (46) and at least one core outlet (48); a neutron reflector (70); a plurality of primary neutronic control elements (50); a secondary neutronic control system (60, 160); a containment vessel (40) substantially surrounding the gas-cooled moderated nuclear reactor core and allowing a gas to flow through both the containment vessel and the core; a fluid circuit (90) to receive hot gas from a containment vessel outlet (44) and deliver cooled gas to the containment vessel inlet (42); and an open Brayton power system coupled to the fluid circuit via a heat exchanger (92), the open Brayton power system comprising: a compressor (102); at least one turbine (104, 106); and a generator (108); the open Brayton power system being arranged such that the at least one turbine is configured to drive the compressor and the generator.

A nuclear fission power plant (10) comprising: a gas-cooled moderated nuclear reactor core (20), the gas-cooled moderated nuclear reactor core comprising: a fuel (30); a moderator (35); and at least one core inlet (46) and outlet (48); a neutron reflector (70); a plurality of primary neutronic control elements (50); a secondary neutronic control element (60); a containment vessel (40) substantially surrounding the gas-cooled moderated nuclear reactor core comprising a containment vessel inlet (42) and outlet (44) defining a flow path therebetween such that gas following the flow path flows from the containment vessel inlet towards the containment vessel outlet via the gas-cooled moderated nuclear reactor core; a fluid circuit (90) configured to receive hot gas from the containment vessel outlet and deliver cooled gas to the containment vessel inlet; and a Rankine power system connected to a generator (108) to generate electrical power.

A molten salt nuclear reactor of the fast neutron reactor type may be designed as a cylindrical shell in the reactor vessel free of moderator or at the very least of a moderator enabling a reactor to be qualified as a thermal neutron reactor, which may make it possible to effectively separate the fluid zones between those delimited at its periphery in which the heat exchanger(s) exchanging heat between primary and secondary circuit is (are) arranged and the zone inside the shell of which the bottom defines the reactor core within which the nuclear fission chain reactions occur, and a neutron reflector at the periphery of the core makes it possible to use a plurality of types of fuel liquid.

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) at least partially extending within the core; a neutron reflector (60) disposed around a periphery of the core; a plurality of neutronic control elements (50) disposed around the periphery of the core; a fluid circuit (80) comprising a first (82) and second (86) heat exchangers and a pump (84), wherein the heat pipes and first heat exchanger transfer heat from the core to a working fluid of the fluid circuit; and an open Brayton power system comprising: a compressor (102); a turbine (104), (106); and a generator (108); the open Brayton power system arranged such that air flows through the compressor, the second heat exchanger, and the turbine, wherein the heat in the working fluid is transferred to the compressed air from the compressor via the second heat-exchanger, and the turbine drives the compressor and generator.

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.

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) at least partially extending within the core; a neutron reflector (60) disposed around a periphery of the core; a plurality of neutronic control elements (50) disposed around the periphery of the core; a fluid circuit (80) comprising a first (82) and second (86) heat exchangers and a pump (84), wherein the heat pipes and first heat exchanger transfer heat from the core to a working fluid of the fluid circuit; and an open Brayton power system comprising: a compressor (102); a turbine (104), (106); and a generator (108); the open Brayton power system arranged such that air flows through the compressor, the second heat exchanger, and the turbine, wherein the heat in the working fluid is transferred to the compressed air from the compressor via the second heat-exchanger, and the turbine drives the compressor and generator.

The invention particularly relates to a device for generating thermal neutrons for thermal neutron imaging, comprising: A neutron generator (2); Neutron moderator (4), A thermal neutron reflector (6) at the exit from the moderator and The present invention relates to a device comprising:

Molten salt nuclear reactor, of the fast neutron type, with a safety vessel surrounding the reactor vessel and a drain tank below the vessels. The invention relates to a fast neutron nuclear reactor (1) comprising: a nuclear reactor vessel (2) filled with a molten salt fuel bath, the interior of the vessel being devoid of a moderator material; a neutron reflector (8), in the form of a shell arranged around the reactor vessel; an assembly of a plurality of neutron-absorbing rods (10), mounted movably in vertical translation around the reactor vessel and inside the neutron reflector, between an absorption position in which they absorb up to a predetermined reactivity threshold value, and a clearance position in which they absorb up to the predetermined reactivity threshold value, during reactor operation. Figure for the abstract: fig.3.

A nuclear reactor with sealed, individually cooled solid fuel assemblies operating nominally via heat pipes. The invention essentially consists of a nuclear reactor operating in the fast neutron spectrum, cooled by a network of one or more heat pipes. At least a portion of the evaporator of one or more heat pipes is partially housed with one or more solid fuel pellets confined in a cladding within a sealed assembly partially filled with a liquid metal bath, which can be described as a thermal seal between the fuel rod cladding and the heat pipes. The reactor core consists of a network of these sealed assemblies (fuel rod(s) and heat pipe(s) immersed in a liquid metal bath), arranged within a vessel surrounded by a neutron reflector. Figure for the abstract: Fig. 1

A nuclear fission power plant (10) comprising: a gas-cooled moderated nuclear reactor core (20), the gas-cooled moderated nuclear reactor core comprising: a fuel (30); a moderator (35); and at least one core inlet (46) and outlet (48); a neutron reflector (70); a plurality of primary neutronic control elements (50); a secondary neutronic control element (60); a containment vessel (40) substantially surrounding the gas-cooled moderated nuclear reactor core comprising a containment vessel inlet (42) and outlet (44) defining a flow path therebetween such that gas following the flow path flows from the containment vessel inlet towards the containment vessel outlet via the gas-cooled moderated nuclear reactor core; a fluid circuit (90) configured to receive hot gas from the containment vessel outlet and deliver cooled gas to the containment vessel inlet; and a Rankine power system connected to a generator (108) to generate electrical power.

A nuclear reactor (109 configured for extra-terrestrial use comprising a nuclear reactor core (20) with UO2 fuel (30), a moderator (60), and a containment vessel (40). A neutron reflector (70) is disposed around a periphery of the nuclear reactor core, and a plurality of control drums (50) disposed around the periphery of the nuclear reactor core. A fluid circuit (90) is configured to receive hot gas from the nuclear reactor core and deliver cooled gas to the nuclear reactor core. An electricity generating system (91) comprising a closed Brayton cycle engine is coupled to the fluid circuit so as to generate an electrical current.

The invention relates to the technical field of radiation experiments, and discloses an animal experiment anti-radiation protection device which comprises a base and a neutron moderation plate fixed on the base, and further comprises a neutron reflection plate arranged on the base in a sliding manner, and a neutron absorption plate is embedded in one surface of the neutron moderation plate and is octagonal; the self-hooping part is arranged in the mouse sleeve; the protecting part is arranged on the mouse sleeve and is connected with the self-hooping part; the cleaning and spraying part is arranged in the mouse sleeve and is connected with the protecting part; the dose of thermal neutrons is optimized through the neutron moderation plate, the upper sleeve and the lower sleeve are matched to ensure that only tumors are exposed to a thermal neutron area, irradiation damage to other parts of a mouse is reduced, push-pull of the upper sleeve drives the L plate to move along the guide groove, the T sleeve rotates in a matched mode, the strap is controlled to be tightened or loosened, and during tightening, the strap and the lower sleeve form a constraint space to fix the mouse; when the mouse is relaxed, the rubber band elastic auxiliary hoop rebounds, the mouse is released, manual binding is not needed, and the operation process is simplified.

A nuclear fission power plant (10) configured for extra-terrestrial use, the nuclear fission power plant comprising: an unmoderated nuclear reactor core (20), the unmoderated nuclear reactor core comprising an unmoderated fuel (30); a neutron reflector (70) disposed around a periphery of the unmoderated nuclear reactor core; a plurality of primary neutronic control elements (50); a plurality of heat pipes (40), each heat pipe comprising a first portion (41) extending within the unmoderated nuclear reactor core and a second portion (42) extending beyond an end of the unmoderated nuclear reactor core; and a plurality of thermoelectric generators (80), wherein a plurality of thermoelectric generators are coupled to each heat pipe, each thermoelectric generator having a hot first end coupled to the second portion of a corresponding heat pipe and a cold second end configured to radiate heat.

This invention relates to the field of radiation experiment technology and discloses an animal experiment radiation protection device, including a base and a neutron moderator plate fixed on the base. It further includes: a neutron reflector plate slidably disposed on the base, with an octagonal neutron absorber plate embedded on one side of the moderator plate; a self-closing part disposed inside a mouse sleeve; a removal part disposed on the mouse sleeve and connected to the self-closing part; and a cleaning spray part disposed inside the mouse sleeve and connected to the removal part. This invention optimizes the thermal neutron dose through the neutron moderator plate, and, in conjunction with the upper and lower sleeves, ensures that only the tumor is exposed to the thermal neutron region, reducing radiation damage to other parts of the mouse. The push-pull mechanism of the upper sleeve drives the L-plate to move along the guide groove, and the T-tube rotates accordingly, controlling the tightening or loosening of the closing strap. When tightened, the closing strap and the lower sleeve form a restraint space to fix the mouse; when loosened, the elastic band assists the closing strap to rebound and release the mouse, eliminating the need for manual binding and simplifying the operation process.