43results about "Energy production using thermoelectric elements" patented technology

The invention relates to the technical field of nuclear reactor safety, and particularly discloses a reactor waste heat export, recovery and comprehensive utilization system and method based on a heat pipe, and the system comprises a nuclear energy generation system, a secondary loop energy conversion system, a primary loop waste heat discharge system, a secondary loop waste heat discharge system, and a waste heat recovery and comprehensive utilization system. According to the waste heat recycling system, the heat pipe can be used for heat transfer and storage under the peak regulation operation condition, the nuclear heat use efficiency is remarkably improved, the requirements of various types of energy sources such as electricity and heat are met, and passive export of reactor core waste heat can be achieved through multi-natural-circulation coupling cooperative operation under the condition of a whole-field outage accident. By means of the efficient heat transfer characteristic and the modularization characteristic of the heat pipes, independent operation of the heat pipes can be achieved, the problem of single-point failure of the system can be avoided, meanwhile, separation of a reactor coolant and a cooling medium of a waste heat removal system can be achieved, the inherent safety of a nuclear reactor is remarkably improved, and the requirements of multi-purpose scenes are met; and the purpose of fully utilizing resources is achieved.

A controlled reactor comprises a reactor core thermally coupled to one or more heat pipes and an active cooling loop. A fluid may be circulated through the active cooling loop. A heat exchanger is thermally coupled to the active cooling loop and extracts heat from the fluid as the fluid is circulated through the active cooling loop. A heating system may be provided to deliver the heat extracted by the heat exchanger to a community. A thermoelectric generator may be provided to convert heat extracted by the heat pipes to electricity for delivery to the community.

The embodiment of the invention relates to the field of devices for obtaining electric energy from radioactive sources, in particular to a nuclear power source using a heat pipe for heat dissipation. The device comprises a reaction assembly, a power generation assembly and a heat dissipation assembly. The reaction assembly comprises a reactor core and a shielding piece located above the reactor core, the reactor core is used for providing heat, and the shielding piece is used for shielding radiation generated by the reactor core; the power generation assembly is arranged in the reactor core and is used for converting heat provided by the reactor core into electric energy; the heat dissipation assembly is arranged in the reactor core, extends out of the reactor core and is used for discharging waste heat from the reactor core to the outside of the reactor core; wherein the heat dissipation assembly comprises a plurality of heat pipes, and each heat pipe is arranged in the reactor core and extends to the outside of the reactor core; the heat pipe is in heat conduction connection with the reactor core, and waste heat can be absorbed by the heat pipe arranged in the reactor core and discharged to the outside of the reactor core through the heat pipe extending to the outside of the reactor core. The nuclear power supply provided by the embodiment of the invention is beneficial to reducing energy loss and improving the power generation efficiency of the nuclear power supply.

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 thermal power reactor (100) includes a reactor core (102) that generates thermal energy and a solid state thermal conductor (106) extending into and thermally integrated with the reactor core (102). The solid state thermal conductor (106) transfers thermal energy generated by the reactor core (102) away from the reactor core (102).

The invention discloses a small nuclear reactor heat energy recovery system based on thermoelectric conversion. The system comprises a reactor pressure vessel, a pressure stabilizer, a steam generator, a main pump, a heat exchanger, a cooling water pump, a cooling water inlet, a cooling water outlet and a thermoelectric conversion device, the reactor pressure vessel, the steam generator, the heat exchanger and the main pump are sequentially connected to form a thermal loop of the system, high-pressure water in the thermal loop absorbs heat released by nuclear fission in the reactor pressure vessel, and the cooling water inlet, the cooling water pump, the heat exchanger and the cooling water outlet are sequentially connected to form a cold loop of the system. High-pressure water in the hot loop heats the hot side surface of the thermoelectric conversion device, cooling water in the cold loop cools the cold side surface of the thermoelectric conversion device, heat is transmitted to the cold loop from the hot loop through the thermoelectric conversion device under the driving of temperature difference, and part of heat energy is directly converted into electric energy through thermoelectric conversion. And the heat energy of the small nuclear reactor is recycled.

A system includes a nuclear reactor having a plurality of fuel rods of radioactive decay material distributed within and embedded within a heat exchange matrix. A plurality of coolant tubes is distributed within and embedded within the heat exchange matrix, interspersed with the plurality of fuel rods. The heat exchange matrix is configured to conduct heat from the fuel rods to the coolant tubes.

A thermal power reactor is provided. The thermal power reactor includes a reactor core arranged to generate thermal energy and a solid state thermal conductor including a graphene based metamaterial. The solid state thermal conductor extends into and is thermally integrated with the reactor core. The solid state thermal conductor is arranged to transfer thermal energy generated by the reactor core away from the reactor core.

A power generation system, such as a nuclear power generation system, is described. An exemplary power generation system includes a heat source, a heat pipe, and a thermophotovoltaic cell. The heat pipe includes a first region and a second region. The first region is positioned to absorb heat from the heat source, and the second region is positioned to radiate at least a portion of the absorbed heat as thermal radiation from the heat pipe. The thermophotovoltaic cell is positioned to receive thermal radiation from the second region of the heat pipe and convert at least a portion of the thermal radiation into electrical energy. The power generation system may further include another heat pipe positioned to remove waste heat from the thermophotovoltaic cell.

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 system and method for a Scalable Liquid Metal cooled small Modular (SLIMM) reactor wherein the reactor vessel in the upper plenum is conductively coupled to the evaporator sections of the liquid metal heat pipes laid on the outside of the vessel wall.

An energy production device may include a core configured to heat a heat transmission fluid, an energy harnessing device configured to convert heat into electrical energy and a heat transfer device positioned over the core configured to receive the heat transmission fluid and transfer the heat to the energy harnessing device. The energy production device may further include a vibration isolator positioned between the energy harnessing device and the heat transfer device. The vibration isolator may be configured to secure the energy harnessing device to the heat transfer device and substantially prevent the transmission of motion from the energy harnessing device to the heat transfer device.

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 reactor includes a reactor vessel containing an alkali metal thermoelectric converter. The bottom part of the vessel contains liquid alkali metal. A reactor core is arranged in the vessel and includes fuel rods. The surface of each fuel rod is provided with a first liquid absorption core. The bottom part of the reactor core is provided with second liquid absorption cores which are connected to the first liquid absorption cores. The cores are together configured to use capillary action to pump liquid alkali metal to an upper portion of an outer surface of the fuel rods, where the liquid alkali metal is vaporized into alkali metal vapor. The converter divides the inside of the reactor vessel into a high-pressure vapor chamber and a low-pressure vapor chamber. The converter is configured to receive alkali metal vapor from the high-pressure vapor chamber for use in electric power generation.

A controlled reactor comprises a reactor core thermally coupled to one or more heat pipes and an active cooling loop. A fluid may be circulated through the active cooling loop. A heat exchanger is thermally coupled to the active cooling loop and extracts heat from the fluid as the fluid is circulated through the active cooling loop. A heating system may be provided to deliver the heat extracted by the heat exchanger to a community. A thermoelectric generator may be provided to convert heat extracted by the heat pipes to electricity for delivery to the community.

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 invention provides a corundum mullite ceramic material, a molybdenum metal heterogeneous component and a brazing manufacturing method and application of the corundum mullite ceramic material and the molybdenum metal heterogeneous component. The corundum mullite ceramic takes corundum and mullite as main crystal phases and is prepared by sintering corundum micro powder and mullite at high temperature. The corundum mullite ceramic material has better thermal shock resistance while having better mechanical properties such as strength, toughness, impact resistance and the like, and can be used as an insulating material for a thermoelectric conversion device instead of aluminum oxide ceramic. According to the corundum mullite ceramic-molybdenum metal heterogeneous component and the brazing manufacturing method thereof, corundum mullite ceramic and molybdenum metal are welded together mainly through a brazing process, so that a corundum mullite ceramic and molybdenum metal brazed joint which is high in connection strength, stable and reliable is obtained. Therefore, the corundum mullite ceramic-molybdenum metal heterogeneous component can be used in a thermoelectric conversion device.

The invention discloses a microminiature static liquid fuel reactor and a noiseless thermoelectric conversion method thereof, and belongs to the technical field of nuclear engineering. The reactor core comprises a reactor core body filled with liquid fission fuel; the natural negative feedback system comprises a first negative feedback unit formed by the thermal expansion effect of the liquid fission fuel and a second negative feedback unit formed by a plurality of gas expansion modules; the thermoelectric conversion system comprises a heat pipe in direct contact with the liquid fission fuel and a thermoelectric conversion assembly integrated on the heat pipe; the sensing and control system comprises a plurality of temperature sensors and neutron detectors, a control rod, a driving mechanism and a control system; wherein the control system judges whether the adjustment of the natural negative feedback system is sufficient or not based on the monitoring data of the temperature sensor and the neutron detector, and regulates and controls the position of the control rod when the adjustment is judged to be insufficient so as to maintain the stable power of the reactor core, and the high-reliability operation of the reactor in the whole life period can be ensured.

Embodiments of the present application relate to the field of nuclear reactors, and in particular to a thermionic reactor. The thermionic reactor provided by embodiments of the present application comprises: a thermionic reactor body configured to convert heat generated by the thermionic reactor body into electrical energy; an electromagnetic pump configured to drive circulation of a coolant of the thermionic reactor body; and a start-up power supply configured to drive the electromagnetic pump to drive circulation of the coolant before the thermionic reactor body is operated. Since the start-up power supply is configured to drive the electromagnetic pump before the thermionic reactor body is operated, self-power supply of the electromagnetic pump during the reactor start-up process can be achieved, which does not rely on an external power supply and drives the coolant to flow to take away excess heat of the thermionic reactor body; after the reactor start-up is completed and a normal operation stage is entered, the start-up power supply can continue to supply power to the electromagnetic pump and other system devices.

The application discloses a modular nuclear reactor power supply device, which comprises one or more power output subsystem cabin sections; the power output subsystem cabin section comprises a cabin shell, a final heat sink, a power adapter device, and a reactor, a helium-xenon thermoelectric conversion loop and a shadow shielding structure arranged in the cabin shell; a coolant channel is formed in the reactor, the coolant channel is filled with a helium-xenon mixed gas, the helium-xenon mixed gas is circulated in the helium-xenon thermoelectric conversion loop to export the heat of the reactor core and generate electric energy; the power adapter device converts the electric energy output by the helium-xenon thermoelectric conversion loop into a desired voltage value matched with a load end and then exports the electric energy to the load end; the power adapter device is connected with multiple power output subsystem cabin sections to realize power output in a parallel mode. Compared with the existing problems of insufficient chemical energy, solar energy and decay energy, the application can generate heat energy through a continuous chain fission reaction and realize continuous supply of electric energy through a thermoelectric conversion loop, and the energy density is high.

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.

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 structured plasma cell includes a first electrode including a first plurality of micro-cavities and a first plasma disposed within one or more micro-cavities of the first plurality of micro-cavities. The structured plasma cell also includes a second electrode including a second plurality of micro-cavities and a second plasma disposed within one or more micro-cavities of the second plurality of micro-cavities. The structured plasma cell also includes an inter-electrode gap disposed between the first electrode and the second electrode.

A structured plasma cell includes a first electrode including a first plurality of micro-cavities and a first plasma disposed within one or more micro-cavities of the first plurality of micro-cavities. The structured plasma cell also includes a second electrode including a second plurality of micro-cavities and a second plasma disposed within one or more micro-cavities of the second plurality of micro-cavities. The structured plasma cell also includes an inter-electrode gap disposed between the first electrode and the second electrode.

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 electric power source in which an electron collector and an electron emitter, having a higher work function than the electron collector, are connected peripherally by a wire and placed very close together. An electric potential difference develops between the electron collector and the electron emitter as electrons spontaneously flow through the wire from the electron collector to the electron emitter due to the difference in work functions. With the electron collector and electron emitter positioned extremely close together, the small electric potential difference creates a strong electric field. The strong electric field allows field emission of electrons from the electron emitter. The emitted electrons then cross the small gap to the electron collector, completing the electric circuit, allowing a continuous electric current to flow, making this device an electric power source.

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.

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.