38results about "Power plants using nuclear energy" patented technology

A mobile fusion device (MFD) comprises three main sections: the MFD reactor (467), MFD support sub-systems (468), and the MFD support and fuel injection sub-systems (469), which are indicated by broken lines in Figure 1 The MFD reactor (467) is where the Deuterium and Tritium fuel is heated to high enough temperatures and densities and confinement times that fusion occurs, releasing neutrons that are absorbed in and heats up the 17Li-83Pb breeder blanket where more Tritium fuel is bred and where heat is transferred to Helium coolant. The MFD support sub-systems (468) houses auxiliary power units that generate electricity to power the electrical sub-systems of the MFD, and houses the MFD control computer, and where the Helium coolant is cryogenically cooled and purified, and where the 17Li-83Pb breeder blanket fluid is purified by separating and storing Deuterium fuel and Tritium fuel and Helium coolant, and where a Helium heat exchanger is located. The MFD support and fuel injection sub-systems (469) houses Deuterium and Tritium neutral beam injection plasma heating systems and a Deuterium and Tritium fuel gas puffer system and a Deuterium and Tritium fuel storage and pellet manufacturing system, and where the 17Li-83Pb breeder blanket fluid is purified by separating and storing Deuterium fuel and Tritium fuel and Helium coolant, and where a Helium heat exchanger is located, and where the Helium coolant is cryogenically cooled and purified, and houses auxiliary power units that generate electricity to power the electrical sub-systems of the MFD. The MFD is housed within a multi-layered pressurised outer containment pod MLP, which has a multi-layered pressurised rear access hatch MLH. The MFD is mounted on a sliding raft SR for ease of access.

The invention discloses a supercritical carbon dioxide natural circulation experimental device and experimental method under a swing condition, and belongs to the field of new working medium nuclear energy system experiments, and the supercritical carbon dioxide natural circulation experimental device comprises a swing simulation platform, a natural circulation loop arranged on the swing simulation platform and a monitoring mechanism, the natural circulation loop comprises an ascending section, a first horizontal section, a descending section and a second horizontal section which are communicated in sequence, a preheating assembly and a heating assembly which are communicated in sequence are arranged on the ascending section, the inlet end of the preheating assembly is further communicated with the vacuumizing mechanism and the carbon dioxide supply mechanism, and a cooling assembly is arranged on the first horizontal section. By adopting the supercritical carbon dioxide natural circulation experimental device and experimental method under the swinging condition, the operation characteristic research on supercritical carbon dioxide natural circulation under the unsteady state motion of the ship and the ocean condition can be carried out, so that the internal influence mechanism of the swinging condition on a natural circulation system can be researched subsequently.

The invention provides a positive pressure type radiation shielding putty pouring method and pouring device using self weight, the method and device are used for a nuclear power reactor cabin shielding structure grillwork, and the shielding putty pouring method comprises the steps that at least one pouring hole is formed in the top end face of the nuclear power reactor cabin shielding structure grillwork; at least one vent hole is formed in the top end face of the nuclear reactor cabin shielding structure grillwork; a pouring pipeline is externally connected to the pouring hole; a filling device is connected to the pouring pipeline, and shielding putty is poured into the nuclear power reactor cabin shielding structure grillwork through the filling device; after the nuclear power reactor cabin shielding structure grillwork is filled with shielding putty, the shielding putty with the first height is left in the pouring pipeline; taking down the filling device; and after the shielding putty is dried, the shielding putty extruded out of the pouring pipeline and the vent holes is removed, and the pouring pipeline and the vent holes are filled and leveled up with the shielding putty. The pressure intensity generated by the weight of the shielding putty is utilized to drive the putty to fill the stacking cabin supporting structure grillwork, a cavity above the shielding putty is basically eliminated, and bubbles in the shielding putty are discharged.

Systems and methods for utilizing nuclear-based marine craft to generate electricity for external or grid usage are disclosed. In accordance with some embodiments, the system may include a nuclear-based marine craft having a propeller shaft and an electrical generator coupled external to the marine craft and configured to transmit generated electricity. In accordance with some other embodiments, the system may include a nuclear-based marine craft having a nuclear reactor and a turbine, a dock or barge having its own turbine and electrical generator, a steam outlet pipe connecting the nuclear reactor to the dock or barge turbine, and a steam inlet pipe connecting the dock or barge turbine back to the nuclear reactor, whereby heated steam from the nuclear reactor spins the dock or barge turbine, which then powers the electrical generator on the dock or barge to generates electricity.

The application provides a method and system for controlling air-borne radioactivity in a control area cabin of a water surface nuclear power ship. A gradient negative pressure is formed in the control area cabin of the nuclear power ship, such as a nuclear power plant containment cabin, an auxiliary cabin, a pollution monitoring and decontamination cabin, and an access passage cabin, by using facilities such as an exhaust fan and a negative pressure compressor, so that the air-borne radioactivity generated during normal operation of the nuclear power plant is controlled. The application can better limit the range of air-borne radioactivity in the control area cabin, prevent the air-borne radioactivity from spreading and leaking to other cabins, and provide strong protection for the radiation safety of personnel on the nuclear power ship.

A heat engine system 100 comprises a working fluid flow circuit with a compressor 300, heat source 400 and turbine 500. The circuit is within a housing 600 defining a sealed reservoir. A first duct 80

Systems and methods for utilizing nuclear-based marine craft to generate electricity for external or grid usage are disclosed. In accordance with some embodiments, the system may include a nuclear-based marine craft having a propeller shaft and an electrical generator coupled external to the marine craft and configured to transmit generated electricity. In accordance with some other embodiments, the system may include a nuclear-based marine craft having a nuclear reactor and a turbine, a dock or barge having its own turbine and electrical generator, a steam outlet pipe connecting the nuclear reactor to the dock or barge turbine, and a steam inlet pipe connecting the dock or barge turbine back to the nuclear reactor, whereby heated steam from the nuclear reactor spins the dock or barge turbine, which then powers the electrical generator on the dock or barge to generates electricity.

A reactor control system (100) for a nuclear fission reactor system comprising a reactor unit (300) having a core (302) with a central axis (320) extending along the length of the core (302). The reactor unit (300) comprises a first region (310) disposed within the core (302) and a second region (312) disposed outside the core (302). The control system (100) comprises a control duct (200) having a first portion (210) configured to extend through the first region (310) and a second portion (220) configured to extend through the second region (312). The duct (200) is filled with a series of control units (400), each of which is configured to travel along the control duct (200).

An emergency release device comprises: a release assembly configured to receive molten salt from a ship equipped with a reactor vessel in which the molten salt flows; and a valve assembly configured to, in an abnormal state where a temperature of the reactor vessel is not within a predetermined range, allow the molten salt to flow from the reactor vessel into the release assembly and to be connected to the release assembly while the molten salt flows from the reactor vessel into the release assembly.

Disclosed is an energy-independent smart port system using SMR-based surplus power. When an SMR-powered vessel docks at a port while the reactor is in operation, the energy-independent smart port system uses relevant technology and equipment to supply surplus power from the SMR-powered vessel to the port in consideration of safety regulations and the characteristic that restarting the reactor of the SMR-powered vessel requires significant time and cost, stably increase the energy independence of a smart port, and can reduce marine air pollutant emissions.

To provide a compact reactor unit.SOLUTION: A reactor control system (100) for a nuclear fission reactor system comprising a nuclear reactor unit (300) having a reactor core (302) with a central axis (320) extending along the length of the reactor core (302). The nuclear reactor unit (300) comprises a first region (310) provided in the reactor core (302) and a second region (312) provided on the outside of the reactor core (302). The control system (100) comprises a control duct (200) having a first portion (210) configured to extend through the first region (310) and a second portion (220) configured to extend through the second region (312). The duct (200) is filled with a series of control units (400), and each of the control units (400) is configured to travel along the control duct (200).SELECTED DRAWING: Figure 3

Heat engine system (100, 1100). The heat engine system (100, 1100) comprises a compressor (300) having an inlet (302) and an outlet (304), a heat source (400) having an inlet (402) and an outlet (404), and a turbine (500) having an inlet (502) and an outlet (504). The compressor (300), the heat source (400), and the turbine (500) define a portion of a working fluid flow circuit (700). The heat engine system further comprises a housing (600) operable to be sealed to define a reservoir (602) in which the compressor (300), the heat source (400), the turbine (500), and the working fluid flow circuit (700) are located. The working fluid flow circuit (700) further comprises a compressor-to-heat source duct (800) extending between the compressor outlet (304) and the heat source inlet (402), a heat source-to-turbine duct (802) extending between the heat source outlet (404) and the turbine inlet (502), and a turbine-to-compressor duct (804) extending between the turbine outlet (504) and the compressor inlet (302). A bleed valve (806) is provided in flow communication with the compressor outlet (304) and operable to bleed working fluid into the reservoir (602). An intake valve (808) is provided in flow communication with the compressor inlet (302) and operable to allow working fluid to pass from the reservoir (602) to the compressor inlet (302).

The invention discloses a ventilation cross-medium aircraft based on a nuclear heat source and a navigation method, belongs to the technical field of cross-medium aircrafts, and aims to solve the problem that the water entry speed is difficult to break through a critical threshold value due to the fact that the water entry impact load is large and hydrodynamic resistance is coupled with a cavitation effect during interface conversion. The core technical problem of the cross-medium aircraft in the interface conversion stage is effectively solved, the dual-mode cavitator on the head is integrated with the ventilation nozzle and the disc cavitator structure, function switching of different navigation stages can be achieved in combination with an internal driving assembly, a head air film can be formed during air patrol, flight resistance can be reduced, and the function switching efficiency can be improved. The high-temperature gas discharge channel is matched with the nuclear heat source steam generator, so that a thermal boundary layer can be formed before the aircraft enters the water, the influence of the impact in the water on the aircraft is further weakened, and the structural damage caused by overlarge impact load in the traditional design is avoided; and the structural reliability and stability in the cross-medium conversion process are improved.

The application discloses a marine bottom shielding structure combining a cabin bottom shielding structure and a stack bottom shielding structure, which comprises the cabin bottom shielding structure and the stack bottom shielding structure located on the lower plate of the double bottom of a ship body, and a stack cabin shielding structure and a primary shielding structure located on the upper plate of the double bottom of the ship body, wherein the primary shielding structure is wrapped outside a reactor pressure vessel, the stack cabin shielding structure is located outside the primary shielding structure, the cabin bottom shielding structure is located outside the stack bottom shielding structure, and the stack bottom shielding structure is located below the primary shielding structure. The marine bottom shielding structure combining the cabin bottom shielding structure and the stack bottom shielding structure has simple structure, can form a complete radiation shielding system together with the stack cabin shielding structure, the primary shielding structure and seawater below the ship body, and can weaken the radiation leakage of the stack cabin to the surrounding area to the maximum extent, so as to ensure the radiation safety of personnel and equipment in the surrounding area.

The present invention relates to a nuclear-powered ship with improved stability, the ship comprising: a nuclear reactor, disposed inside a hull, for generating steam from thermal energy produced during the nuclear fission process; a turbine installed in the hull and connected to the nuclear reactor, and rotating from the collision and reaction forces of colliding steam; and a rotor disposed inside the hull and rotating about a spin shaft, a gimbal rotatably supporting the spin shaft, and a gyroscopic stabilizer preventing the ship from tilting by means of precessional motion of a frame that rotatably supports the gimbal, wherein the turbine is mounted on the spin shaft of the gyroscopic stabilizer to transmit rotational force thereto, and the gyroscopic stabilizer comprises a generator mounted on the spin shaft, power being generated by the generator activated by the rotation of the spin shaft and rotor by the turbine.

The application belongs to the field of ship design, and particularly relates to a nuclear power icebreaker safety shell energy-absorbing buffer protection structure applied to ice resistance of the nuclear power icebreaker. The structure comprises three regions, namely, an impact resistance region, a transition region and a reactor cabin. The impact resistance region is connected with the transition region, the transition region is connected with the reactor cabin, and the transition region is located between the impact resistance region and the reactor cabin. The application has the following beneficial effects: 1) the safety shell is better protected by setting an additional isolation cabin and its accessory structure outside the safety shell; 2) the stress distribution of the impact load transmission to the ship middle component is improved by setting a supporting longitudinal girder, so that the position of the high stress area is changed positively; and 3) the application has the characteristics that the stress is obviously weaker than that of the impact resistance region and the reactor cabin component, and a large number of openings are designed, so that when the ship is impacted by an extreme event, a clear buffer zone and a fracture interface are formed in the region, and the integrity of the reactor cabin safety shell is effectively protected.

A modular nuclear-powered unmanned underwater vehicle (UUV) belongs to the category of underwater equipment. This invention addresses the shortcomings of conventionally powered UUVs, such as limited functionality and short endurance, which are insufficient to meet the demands of deep-sea exploration and long-duration navigation. The invention comprises the UUV body, a monitoring system, a remote communication system, a control system, a buoyancy-cooling system, a thermoelectric conversion system, a power system, a shielding system, and a passive waste heat removal heat exchanger. The UUV body, monitoring system, remote communication system, buoyancy-cooling system, thermoelectric conversion system, power system, and passive waste heat removal heat exchanger are connected to the control system. The thermoelectric conversion system supplies power to the UUV body and the buoyancy-cooling system, while the power system supplies power to the UUV body, monitoring system, remote communication system, and control system. The heat exchanger is mounted outside the hot end of the thermoelectric conversion system, and the shielding system is located at both ends of the thermoelectric conversion system. This invention is primarily used for deep-sea exploration.

This invention discloses an Arctic submersible transport system adaptable to both nuclear and conventional diesel power, belonging to the field of Arctic transport equipment technology. The system includes a dual-power mode compatible submersible transport platform module, a piston-type self-cleaning storage and transport module, a multimodal three-dimensional collaborative operation module, an under-ice communication and navigation module, an intelligent ballast control module, and a safety assurance module. The core platform adopts a modular power compartment design, adaptable to either nuclear or conventional diesel power, and can stably submerge at a depth of 5 meters under 2 meters of Arctic ice, with a rated crude oil carrying capacity of 460,000 tons. It is equipped with multiple unmanned surface vessels, ice-surface hovercraft, and aerial resupply and protection mechanisms to form a three-dimensional collaborative system. The storage and transport module uses a partitioned piston-type oil tank structure, enabling crude oil loading and unloading, self-cleaning, and dynamic control of ballast water. This system enables year-round, all-weather navigation along Arctic routes, mitigating geopolitical risks, balancing long-range economics with construction approval flexibility, and significantly improving the efficiency, safety, and adaptability of polar energy and bulk commodity transportation.

To provide a ship or other vessel that generates electricity so that it can supply power to land when a nuclear reactor is operating at full power. [Solution] A ship and a method for operating a ship. The ship has a power generation system comprising a nuclear reactor and a generator. The nuclear reactor is coupled to the generator to produce electricity. Furthermore, the ship may include a propulsion system comprising an engine and a thruster that receives torque from the engine and moves the ship through the water surrounding the ship. The ship may be part of a temporary power system having an electrical cable that electrically connects the generator to an onshore power distribution system. Multiple buoys may support the electrical cable between the ship and the onshore power distribution system. A method for operating a ship may include the steps of starting the nuclear reactor while the ship is underway and maintaining the nuclear reactor in a standby state.

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

A mobile fusion device (MFD) comprises three main sections: the MFD reactor (467), MFD support sub-systems (468), and the MFD support and fuel injection sub-systems (469), which are indicated by broken lines in Figure 1 The MFD reactor (467) is where the Deuterium and Tritium fuel is heated to high enough temperatures and densities and confinement times that fusion occurs, releasing neutrons that are absorbed in and heats up the 17Li-83Pb breeder blanket where more Tritium fuel is bred and where heat is transferred to Helium coolant. The MFD support sub-systems (468) houses auxiliary power units that generate electricity to power the electrical sub-systems of the MFD, and houses the MFD control computer, and where the Helium coolant is cryogenically cooled and purified, and where the 17Li-83Pb breeder blanket fluid is purified by separating and storing Deuterium fuel and Tritium fuel and Helium coolant, and where a Helium heat exchanger is located. The MFD support and fuel injection sub-systems (469) houses Deuterium and Tritium neutral beam injection plasma heating systems and a Deuterium and Tritium fuel gas puffer system and a Deuterium and Tritium fuel storage and pellet manufacturing system, and where the 17Li-83Pb breeder blanket fluid is purified by separating and storing Deuterium fuel and Tritium fuel and Helium coolant, and where a Helium heat exchanger is located, and where the Helium coolant is cryogenically cooled and purified, and houses auxiliary power units that generate electricity to power the electrical sub-systems of the MFD. The MFD is housed within a multi-layered pressurised outer containment pod MLP, which has a multi-layered pressurised rear access hatch MLH. The MFD is mounted on a sliding raft SR for ease of access.

The invention relates to the technical field of ocean nuclear power systems, in particular to a novel ship power system heat exchange device which comprises a shell, an air inlet is formed in the first end of the shell, and an air outlet is formed in the second end of the shell; the base body is contained in the middle section of the shell, and a plurality of tubular channels extending in the axial direction are formed in the base body; the circumferential outer surface of each heat pipe is coated with a sleeve, each heat pipe is arranged in the corresponding tubular channel, and each heat pipe is coaxial with the corresponding tubular channel; the outer diameter of each sleeve is smaller than the inner diameter of the corresponding tubular channel, so that an annular flow channel is defined between each sleeve and the inner wall of the corresponding tubular channel, and heat exchange working media can flow through the annular flow channels conveniently. Through the configuration, the heat exchange working medium flows through the circumferential outer surface of the sleeve in the axial direction, so that heat in the heat pipe pile is efficiently transferred to the high-pressure heat exchange working medium, and continuous, stable and efficient power output is provided for a ship.

The invention discloses a small nuclear energy underwater unmanned equipment system capable of realizing efficient power generation based on energy storage, which comprises a nuclear reactor system, a heat storage unit and a supercritical carbon dioxide Brayton cycle power system, the temperature difference between the tanks is increased through a heat storage and recovery mechanism; nuclear energy released by the nuclear reactor system is transmitted to the supercritical carbon dioxide Brayton cycle power system through the heat storage unit, and energy conversion is completed through cooperative work of a heater, a steam turbine, a heat regenerator, a precooler and a gas compressor; through the nuclear-storage-circulation coupling design, the core requirements of light weight, long service life and intelligent control of underwater unmanned equipment can be met, and a power technical support is provided for ocean strong national construction.

The invention relates to the field of comprehensive utilization and optimal configuration of energy, in particular to a ship combined power generation system integrating low-temperature refrigeration and hydrogen production, which comprises an SOFC-GT power generation module for providing energy for ship power and ship service load by using a gas turbine; the DARC refrigeration module is used for refrigerating through waste heat generated by the SOFC-GT module, and the refrigeration requirement is met; the PEME hydrogen production module is used for generating oxygen as an oxidant of a cathode of the solid oxide fuel cell, so that the combustion efficiency is improved; the TCPC power generation module is used for reducing the carbon emission in the sailing process and guaranteeing the power demand of the ship; the LNG cold energy utilization subsystem is used for providing cold water for the ship to meet the refrigeration requirement; the carbon dioxide capturing module is used for capturing and storing carbon dioxide, and the storage cost of the ship in the shipping process is reduced. Various energy forms such as electric energy, cold energy, heat energy and hydrogen energy are integrated, systematic consideration is conducted when the system is applied to the ship, and the system is more suitable for the multi-energy requirement of the ship and the complex scene of zero-carbon constraint.

A heat engine system comprises a compressor, a heat source, and a turbine, each having an inlet and an outlet, and which collectively define part of a working fluid flow circuit. The system further comprises a housing operable to be sealed to define a reservoir in which the compressor, heat source, and turbine are located. The working fluid flow circuit further comprises a compressor-to-heat-source duct which extends between the compressor outlet and the heat source inlet, a heat-source-to-turbine duct which extends between the heat source outlet and the turbine inlet, and a turbine-to-compressor duct which extends between the turbine outlet and the compressor inlet. A bleed valve is provided in flow communication with the compressor outlet, operable to bleed working fluid into the reservoir. An intake valve is provided in flow communication with the compressor inlet operable to allow passage of working fluid from the reservoir to the compressor inlet.

This emergency release device comprises: a discharge assembly provided so as to allow molten salt to flow thereinto from a ship having a reactor tank in which molten salt flows; and a valve assembly inducing the molten salt to flow from the reactor tank into the discharge assembly when in a state of emergency in which the temperature of the reactor tank cannot be controlled, the valve assembly being connected to the discharge assembly while the molten salt flows into the discharge assembly.

The invention belongs to the technical field of ships, and discloses a ship nuclear power system and a ship, in the ship nuclear power system, a reactor is used for containing liquid salt and a fission material, the fission material can generate nuclear fission in the reactor so as to generate a large amount of heat and heat the liquid salt, and a heat exchanger is used for allowing the liquid salt and water to enter. The liquid salt and the water can be subjected to heat exchange in the heat exchanger, so that the water is heated to form steam, the liquid salt serves as a heating medium and is used for heating the water, the steam turbine is used for allowing the steam to enter, the steam can push blades of the steam turbine to rotate to output power, and the emergency discharging tank is connected with the reactor. Liquid salt and fission materials in the reactor can enter the emergency discharging tank, so that when the reactor has an accident, the liquid salt and the fission materials in the reactor can be quickly discharged into the emergency discharging tank, high-temperature materials are prevented from continuously remaining in the reactor, the reactor is convenient to cool, and the safety of the reactor is improved. The reactor can be protected to a certain extent.

The emergency release device comprises: a release assembly configured to allow molten salt to flow therein from a vessel having a reactor vessel in which the molten salt flows; and a valve assembly that causes the molten salt to flow from the reactor vessel into the release assembly in an emergency condition in which the temperature of the reactor vessel is not controllable, the valve assembly being connected to the release assembly as the molten salt flows into the release assembly.

Provided is an offshore platform allowing carbon neutral fuel to be produced, stored and supplied, overcoming intermittency of renewable energy, the offshore platform comprising: a main body located offshore; a hydrogen production unit for producing hydrogen via sea water electrolysis using a water electrolysis device and storing the hydrogen; an ammonia production unit, disposed in the main body, for synthesizing, via a first synthesis device, the hydrogen flowing in from the hydrogen production unit with nitrogen in the air to produce ammonia and storing same; a carbon dioxide storage unit, disposed in the main body, for storing carbon dioxide flowing in from the ship; and a methanol production unit, disposed in the main body, for synthesizing, by means of a second synthesis device, the carbon dioxide flowing in from the carbon dioxide storage unit and hydrogen flowing in from the hydrogen production unit to produce methanol and storing same.