36results about "Power plants using nuclear energy" patented technology

The invention relates to a control system and method for a long-term low-power biased loop operation of a multi-loop reactor. The control method comprises a downlink power control method and an uplink power control method. A biased loop operation control system is established, and a scientific and feasible control method is adopted, so that the stable operation and steady output problems of the unit positioned in a low-power state for a long time can be solved when a nuclear powered vessel performs self-propelled marine operation, reactor trip is not needed when the nuclear powered vessel operates at low power for a long time, namely the stable operation and steady output of the unit can be realized, and obvious economic benefits are achieved. The long-term low-power marine operation of the ship is realized, and the application range of the reactor is widened. Moreover, since the reactor trip is not needed in the power switching process, the low-power operation risk is reduced, and the safety and economic efficiency of the unit are greatly improved.

The invention discloses a seabed underwater vehicle. The seabed underwater vehicle comprises a mother underwater vehicle and multiple sub underwater vehicles; the mother underwater vehicle comprises apropulsion system, a course control system, a weapon release system, multiple sub underwater vehicle storage, charging and repairing units, a mother body master control system, a sonar transmitting,receiving and processing system, a mother body gas storage chamber, a nuclear power conversion system and a motor power system; the multiple sub underwater vehicle storage, charging and repairing units cover the whole body of the mother underwater vehicle to be fixedly connected with the mother underwater vehicle; and each sub underwater vehicle storage, charging and repairing unit comprises a subunderwater vehicle. The seabed underwater vehicle can very well replace human beings to execute a series of military missions in the deep sea field; the seabed underwater vehicle can be divided intomultiple small-sized underwater vehicles to realize omnibearing three-dimensional reconnaissance; multiple functions such as intelligence reconnaissance, information transmission and attacking enemy forces are also realized; and activities such as territorial sea cruising, deep sea reconnaissance and deep sea scientific research can be finished.

The invention discloses a supercritical carbon dioxide circulation and sea water desalination coupled vessel nuclear power system which comprises a reactor cabin, a ship cabin and a propelling device,the reactor cabin comprises a high-temperature gas cooled reactor system, and the ship cabin comprises a supercritical carbon dioxide power circulation system and a sea water desalination subsystem.A first-stage intermediate heat exchanger and a second-stage intermediate heat exchanger are arranged on the two sides of a high-temperature gas cooled reactor in the high-temperature gas cooled reactor system correspondingly. The supercritical carbon dioxide power circulation system is coupled with the high-temperature gas cooled reactor system through a first-stage intermediate heat exchanger and a second-stage intermediate heat exchanger. The seawater desalination subsystem is coupled with the supercritical carbon dioxide power circulation system through a precooler and an intercooler. Thepropelling device is connected with the supercritical carbon dioxide power circulation system. Vessel propulsion power and electric power are provided through the supercritical carbon dioxide circulation system, fresh water needed by the whole vessel is provided in cooperation with the sea water desalination system, the vessel is driven to sail in a direct propulsion mode, and the energy conversion rate and the device compactness are improved.

The invention provides a nuclear power supply system for an underwater unmanned submersible vehicle. The nuclear power supply system can improve the inherent safety and unmanned autonomous control capability of a reactor. The system comprises a reactor core, a high-temperature heat pipe, an alkali metal thermoelectric conversion device, a medium-temperature heat pipe, a storage battery and a pressure-resistant shell, wherein the evaporation section of the high-temperature heat pipe is inserted into the reactor core; the condensation section of the high-temperature heat pipe is inserted into the alkali metal thermoelectric conversion device; the alkali metal thermoelectric conversion device comprises a plurality of groups of thermoelectric conversion modules; a heating end of each thermoelectric conversion module is connected with the high-temperature heat pipe; a condensation end of each thermoelectric conversion module is connected with the medium-temperature heat pipe; the condensation section of the medium-temperature heat pipe is connected with the pressure-resistant shell; waste heat is conducted into surrounding seawater; the alkali metal thermoelectric conversion device is further connected with a storage battery; and the alkali metal thermoelectric conversion device converts heat energy into electric energy and stores the electric energy in the storage battery.

The invention discloses a supercritical carbon dioxide circulation switchable vessel power system of a lead-cooled fast reactor. The supercritical carbon dioxide circulation switchable vessel power system comprises the lead-cooled fast reactor, a reactor cabin composed of a primary loop system of the lead-cooled fast reactor, a cabin composed of a switchable supercritical carbon dioxide power circulation secondary loop system and a propelling device. A lead-cooled fast neutron reactor is adopted as a heat source, and ship propulsion power and equipment electric power are output in a supercritical carbon dioxide power cycle mode combining primary reheating, intermediate cooling compression and shunt recompression processes. Effective switching of supercritical carbon dioxide circulation ofan inner cooling mode and a partial cooling mode under different operation requirements is achieved through gate valve opening and closing operation, and the direct propelling device is combined to drive the vessel to sail. The energy conversion efficiency is remarkably improved, the compactness of the power device and the effective load of the vessel are greatly improved, low-energy-consumption and high-performance operation of the vessel is satisfied; according to the invention, a new thought is provided for application of supercritical carbon dioxide circulation in the field of nuclear power vessels.

The invention discloses a nuclear power steam-jet ship propulsion system, which comprises a ship body, a nuclear reactor, a steam generator, a steam, air and water mixing chamber, a jet nozzle, a jet nozzle controller, a water absorption opening and an air absorption opening; the water outlet of a high pressure heating water tank of the nuclear reactor is communicated with the inlet of a U-shaped pipe at the lower part of the steam generator through a pipeline with a pressure stabilizer; the outlet of the U-shaped pipe is communicated with a water recycling opening of the high pressure heating water tank through a pipeline with a main pump; the air absorption opening is communicated with an air jet annular pipe of the steam, air and water mixing chamber through an air-conveying pipe with an air pump; the water absorption opening is communicated with a water supply opening of the steam generator through a pipeline with a water supply pump and communicated with a steam jet annular pipe of the steam, air and water mixing chamber via the hot steam outlet of the steam generator through a steam-conveying pipe; and the water absorption opening is further communicated with a water jet annular pipe of the steam generator through a water-conveying pipe with a water pump. By adoption of the nuclear power steam-jet ship propulsion system, a ship has high energy utilization rate and long endurance mileage, and has no CO2 pollution.

A multi-loop natural circulation experimental device under six-degree-of-freedom motion conditions and a method therefor are provided. The device includes: a six-degree-of-freedom motion simulation platform; a multi-loop main circulation loop including a serpentine pre-heater, an experimental section, two sleeve-type condensers, and a pressurized circulating pump, a voltage stabilizer and related equipment; and a cooling water system including a sleeve condenser, a plate heat exchanger, a cooling tower, a cooling fan, a cooling water tank and related equipment; and an electric heating system including a DC power supply, a low voltage power controller and a transformer. The present invention also provides an experimental method of the device.

The invention discloses an injection machine and steam jet pump boosting mute nuclear-powered submarine. A high temperature air cooling nuclear reactor is used for providing 950 DEG C for performing thermoelectric electricity generation, electricity power drives a motor of an injection machine, a water absorption tube is arranged in the center of the head of the submarine, and a water outlet is formed in the tail of the submarine to be connected with a single or a plurality of water injection tubes; water jetting flows drive the submarine to move, and can be used for adjusting direction and postures, steam of a reactor secondary circuit is used for driving a steam jet water pump, and devices capable of generating noise and sound removing bases are arranged in a vacuum environment, so that a condition that convection current can guide temperature to a people working region; the inner parts of a water absorption tube and a water outlet tube of the pump are subjected to sound removing treatment; in the submarine, the power-driven injection machine is a movable device, and the other devices are device bases in the vacuum environment and are subjected to sound removing treatment. The injection machine and the steam jet pump can work together, so that the injection machine and steam jet pump boosting mute nuclear-powered submarine can quiet move at a high speed.

A low noise shaftless pump-jet nuclear submarine is composed of a shaftless pump-jet propeller and a nuclear submarine main body. The shaftless pump-jet propeller is installed at the tail portion of anuclear submarine, the shaftless pump-jet propeller is integrally composed of a axial-flow type water pump and a high-power circumferential motor, the power density of the high-power circumferentialmotor is high, and the sealing quality of an injection-molding packaged circumferential motor stator and an injection-molding packaged circumferential motor rotor is high; a front annular bearing anda rear annular bearing are made of stainless steel, marine corrosion can be totally and effectively prevented through the shaftless pump-jet propeller, and the position between the circumferential motor stator and the circumferential motor rotor is located by the front annular bearing and the rear annular bearing and is kept steady through the magnetic force of a permanent magnet ring; an inner circle of the stator and an outer circle of the rotor are installed and separated under a sliding fit condition, an annular magnetic gap between the circumferential motor stator and the circumferentialmotor rotor is operated under the condition of water lubrication, and the rolling friction of the front annular bearing and the rear annular bearing is converted into the water lubricating friction; the noise of bearings and gears is not generated, blades of an axial-flow type propeller are in an involute shape, and the noise of blade stirring is low; and the production and the maintenance of thehigh-power circumferential motor is easy, and the cost is low.

The invention discloses a power supply mode selection method based on nuclear power ship operation condition analysis and device. The method comprises the following steps: S10, a ship operation condition and constraints under the ship operation condition are determined; S20, according to the ship operation condition, the operation mode of a reactor is determined; S30, according to the ship operation condition and the operation mode of the reactor, the current available power supply and the capacity, the load type and the power are determined; S40, according to the defense in depth principle ofa power supply and load characteristics of a nuclear power plant, the types and the number n of power supplies are selected; and S50, the capacity and the minimum load rate are verified, if passing the verification, the power supply system operation mode selected and determined by the former steps is determined to be a final result, and if not, adjustment is carried out according to a preset strategy, and the step S30 is carried out and reselection is carried out. The device is used for executing the method. Thus, nuclear power ship operation condition analysis and power supply system operation mode selection under each ship reactor operation condition are solved, and requirements of power supply safety, reliability and stability and the like are met.

The invention provides a method for arranging primary circuit main cabLes in a nucLear power ship. The method incLudes the steps that a working cabin segment is determined, and the current safety LeveL of the main cabLes arranged in the working cabin segment is obtained; according to reLated structure information of the working cabin segment, the trend and instaLLing structure of the main cabLes in the working cabin segment are determined, the type and distance of aLL branched cabLes in the main cabLes are determined, according to the current safety LeveL of the main cabLes arranged in the working cabin segment, the trend and instaLLing structure of main redundant cabLes are determined, the distance of the main cabLes corresponding to the main redundant cabLes is determined, and the type and distance of aLL branched redundant cabLes in the main redundant cabLes are determined; according to the reLated information of the main cabLes in the working cabin segment and the main redundant cabLes, the cabLes are arranged in the working cabin segment. In the impLementation of the method, the designing requirements for the independency of a power suppLy circuit of nucLear safety LeveL redundancy equipment, the independency of power suppLy circuits of nucLear safety LeveL equipment and non-safety LeveL equipment and entity isoLation between the cabLes of different types can be met.

The invention relates to a buffer base suitable for ocean nuclear power platform equipment. The buffer base comprises a buffer module, the buffer module comprises a base panel and a supporting structure thereof, a fixed rigid base and a buffer mechanism, the base panel and the supporting structure thereof comprise a base panel, a main supporting column, a plurality of T-shaped sections and a bottom circular pressing plate, and the T-shaped sections are evenly and symmetrically arranged around the main supporting column in the circumferential direction; the top faces of the main supporting column, the T-shaped profile web and the T-shaped profile panel are all connected with the base panel. The bottom circular pressing plate is provided with a through hole, the bottom face of the T-shaped profile is connected with the bottom circular pressing plate, the main supporting column penetrates through the bottom circular pressing plate through the through hole, and the bottom face of the mainsupporting column is connected with the fixed rigid base through the buffer mechanism. According to the buffer base, the influence of inertia force generated by ship movement on nuclear power platformnuclear safety equipment can be reduced, energy brought by impact is absorbed, and the stable operation environment of the nuclear safety equipment is guaranteed.

The invention provides a configuration system for a special safety disk of a main control room of a nuclear power ship. The system is used in the marine nuclear power ship. The system comprises at least one safety level monitoring unit which uses safety level display screens to monitor safety level equipment and parameters, and at the same time provides a safety level important post-accident parameter monitoring function, at least one non-safety level monitoring unit which consists of a corresponding non-safety level display screen and corresponding manual hard operation buttons, an information recording unit, and an emergency shutdown and special safety facility management button group. According to the invention, the system fills the gap in the technology of the marine nuclear power shipin China, and provides a feasible scheme for developing and manufacturing the marine nuclear power ship; and the special safety disk provided by the invention integrates multiple functions of the main control room in an onshore nuclear power plant, can be arranged in the main control room of various types of nuclear power ships, and is not limited to the size of the main control room of the ship.

The invention relates to an overall arrangement structure of a reactor cabin of a water surface nuclear power ship. The overall arrangement structure comprises the reactor cabin arranged in the middle of the ship. The reactor cabin comprises a nuclear fuel loading and unloading cabin, a spent fuel storage cabin, a containment cabin, a nuclear auxiliary mechanical cabin and a nuclear three-waste treatment cabin, and the five cabins are arranged on a ship cabin bottom void cabin and in two broadside void cabins. According to the structure, the reactor cabin is arranged in the middle of the ship, namely, the middle bears the heaviest weight, it can be ensured that the weight center of the ship is located on the central axis, the stable floating state of the ship can be achieved, inclination (longitudinal inclination and transverse inclination) is avoided, the requirement for ship ballast is lowered, and the situation that extra ballast water is greatly increased to balance the weight of tail arrangement is avoided.

The invention relates to a marine capillary force driven containment vessel heat exporting system which comprises a water tank, a containment vessel is arranged in the water tank, and the outer surface of the containment vessel is provided with a porous structure having capillary driving force on water. According to the heat exporting system, fluid is driven to flow on the surface of the containment vessel through capillary force of the porous structure on the liquid, so that heat in the containment vessel is taken away, continuous power supply to active equipment is not needed, and the safetyprotection effect can still be achieved even under the condition that a power supply is lost.

The invention relates to a modular separable heat supply ship which comprises a ship body, the ship body comprises an outer ring cabin and a two-ring cabin. The two-ring cabin is provided with a steamconversion device used for converting steam and then outputting the converted steam, and the ship body is provided with a first connecting device; and a reactor cabin module which comprises a reactorcabin and is used for converting nuclear power into steam, wherein the reactor cabin module is provided with a second connecting device connected with the first connecting device. The first connecting device is arranged on the ship body, the second connecting device is arranged on the reactor cabin module, and the reactor cabin module is separated from the ship body and replaced with a new reactor cabin module when refueling or overhaul is needed so that rapid switching of heat supply is realized, the shutdown heat supply interruption time is shortened and the construction cost is reduced.

The invention discloses a pressure stabilizer relief system for a deep-sea nuclear power underwater platform, belonging to the field of deep-sea equipment. The pressure stabilizer relief system at least comprises a pressure stabilizer, a pressure relief pipeline, an exhaust manifold and a pressure relief tank; and the pressure stabilizer relief system comprises a pressure stabilizer, a pressure relief pipeline, an exhaust manifold and a pressure relief tank. Three pressure relief pipelines are connected above the voltage stabilizer, and each pressure relief pipeline is provided with an electric gate valve and a safety valve; The three pressure relief pipelines are connected with the exhaust manifold, and the exhaust manifold is connected with the pressure relief box. Water and nitrogen arearranged in the pressure relief box, and the pressure relief box is respectively connected with the spray system and the nitrogen system; One side of the pressure relief tank is part of the deep seanuclear power pressure housing; The top and bottom of the pressure relief tank are connected to the waste treatment system; The utility model solves the problem that the existing pressure stabilizer relief system needs to install an exhaust pipeline on the pressure-resistant shell, which is not conducive to the structural safety of the underwater platform; The pressure stabilizer relieving systemcan be operated reliably in deep sea, and the effect of influence on the pressure-resistant shell can be avoided.

The invention relates to a modularized separable heating ship, which includes: a hull, the hull includes an outer ring cabin and a second ring cabin, and the second ring cabin is provided with a steam conversion device for converting steam to output, so The hull is provided with a first connection device; the reactor compartment module includes a reactor compartment for converting nuclear power into steam, and the reactor compartment module is provided with a second connection device connected to the first connection device; through The first connecting device is arranged on the hull, the second connecting device is arranged on the reactor compartment module, and the reactor compartment module is separated from the hull when refueling or overhaul is required, and replaced The new reactor compartment module is installed to realize rapid switching of heat supply, shorten the time of shutdown and heat supply interruption, and reduce construction costs.

A floating liquefied natural gas (FLNG) driving system based on nuclear power comprises a steam generation module, a nuclear reactor is arranged in a reactor cabin of the steam generation module, and the nuclear reactor is sequentially connected with a steam generator and a main circulating pump to form a first circulating network; heat of saturated steam generated by the steam generator is sequentially provided for the power generation system, the natural gas liquefaction system, the pump set turbine system, the cabin section heating system, the miscellaneous steam system and the upper oil gas treatment and public system. The defects in the prior art are overcome, heat energy converted from nuclear energy is applied to all the systems in the floating device, all the systems are stable, reliable, energy-saving and environment-friendly, and pollution is reduced. Meanwhile, the medium-temperature seawater obtained after dead steam cooling is applied to a fresh water making system, the fresh water demand of a steam system is met, the medium-temperature seawater is effectively utilized, the heat efficiency of the system is improved, and environmental damage is reduced.

The invention relates to the technical field of nuclear power ships, in particular to a nuclear power ship area arrangement structure which comprises a non-control area, a cold changing room, a hot changing room, a decontamination room and a control area. The cold changing room communicates with an access door of the non-control area; The hot changing room communicates with an access door of the control area; a one-way gate is arranged between the outlet of the cold changing room and the hot changing room; a pollution detector is arranged between the outlet of the hot changing room and the cold changing room; and the decontamination room is arranged in the internal compartment of the hot changing room and communicates with the hot changing room. A radioactive contamination area and a non-radioactive contamination area are physically isolated, radioactive contamination diffusion can be effectively prevented, precious space resources can be saved for nuclear power ships, enough places and articles can be provided for workers entering and exiting the control area, and meanwhile, radioactive contamination detection and decontamination can be carried out on personnel and articles leaving the control area.

The invention discloses a layout structure of a nuclear power ship main control room. The layout structure includes a first loop operator station, a second loop operator station, an emergency controlpanel, a backup panel and a crew leader workstation. The first loop operator station, the second loop operator station, the backup panel and the crew leader workstation are each provided with safety level monitoring equipment and non-classified monitoring equipment. The first loop operator station, the second loop operator station and the crew leader workstation are mutually and redundantly configured. The emergency control panel is arranged between the first loop operator station and the second loop operator station, and is used for enabling first loop operators to perform manual shutdown andmanually start engineered safety features in an emergency. The backup panel is arranged on one side of the first loop operator station, and is used for switching a computer information and control system mode to a backup panel mode when the first loop operator station, the second loop operator station and the crew leader workstation are unavailable, and the backup panel directly brings a reactorinto a safe shutdown state to be maintained in the safe shutdown state. The layout structure of the nuclear power ship main control room can be implemented to improve the overall operating safety of anuclear power ship.

The invention provides a method for arranging primary circuit main cabLes in a nucLear power ship. The method incLudes the steps that a working cabin segment is determined, and the current safety LeveL of the main cabLes arranged in the working cabin segment is obtained; according to reLated structure information of the working cabin segment, the trend and instaLLing structure of the main cabLes in the working cabin segment are determined, the type and distance of aLL branched cabLes in the main cabLes are determined, according to the current safety LeveL of the main cabLes arranged in the working cabin segment, the trend and instaLLing structure of main redundant cabLes are determined, the distance of the main cabLes corresponding to the main redundant cabLes is determined, and the type and distance of aLL branched redundant cabLes in the main redundant cabLes are determined; according to the reLated information of the main cabLes in the working cabin segment and the main redundant cabLes, the cabLes are arranged in the working cabin segment. In the impLementation of the method, the designing requirements for the independency of a power suppLy circuit of nucLear safety LeveL redundancy equipment, the independency of power suppLy circuits of nucLear safety LeveL equipment and non-safety LeveL equipment and entity isoLation between the cabLes of different types can be met.

The invention relates to a control system and method for a long-term low-power biased loop operation of a multi-loop reactor. The control method comprises a downlink power control method and an uplink power control method. A biased loop operation control system is established, and a scientific and feasible control method is adopted, so that the stable operation and steady output problems of the unit positioned in a low-power state for a long time can be solved when a nuclear powered vessel performs self-propelled marine operation, reactor trip is not needed when the nuclear powered vessel operates at low power for a long time, namely the stable operation and steady output of the unit can be realized, and obvious economic benefits are achieved. The long-term low-power marine operation of the ship is realized, and the application range of the reactor is widened. Moreover, since the reactor trip is not needed in the power switching process, the low-power operation risk is reduced, and the safety and economic efficiency of the unit are greatly improved.