51results about "Nuclear engineering" patented technology

The present invention is directed to providing a method of producing synthetic fuels and organic chemicals from atmospheric carbon dioxide. Carbon dioxide gas is extracted from the atmosphere, hydrogen gas is obtained by splitting water, a mixture of the carbon dioxide gas and the hydrogen gas (synthesis gas) is generated, and the synthesis gas is converted into synthetic fuels and / or organic products. The present invention is also directed to utilizing a nuclear power reactor to provide power for the method of the present invention.

A process for co-producing synthesis gas and power includes producing a synthesis gas comprising at least CO and H2 by reacting a hydrocarbonaceous feedstock with oxygen, the synthesis gas being at a first temperature, separating air from a compressed air stream by means of at least one ion transport membrane unit thereby producing a permeate stream consisting predominantly of oxygen and a reject stream of oxygen-depleted air at a second temperature which is lower than the first temperature, indirectly heating the reject stream of oxygen-depleted air with the synthesis gas and at least partially expanding, the heated reject stream of oxygen-depleted air through at least one turbine to generate power, producing an at least partially expanded reject stream of oxygen-depleted air, and feeding at least a portion of the permeate stream consisting predominantly of oxygen to the synthesis gas generation stage to provide oxygen for production of synthesis gas.

The invention discloses a nuclear power and low temperature multi-effect sea water desalination coupling cogeneration system, belonging to the technical field of nuclear power utilization and low temperature multi-effect sea water desalination. The system comprises a small-sized nuclear reactor, a vapor generator, a turbine, a vapor converter, a vapor thermal compressor, a low temperature multi-effect evaporator and auxiliary equipment. In the system, the nuclear reactor provides energy so as to drive the vapor generator to generate high pressure vapor, the high pressure vapor enters the turbine and generates electricity through working, part of vapor is extracted out from the turbine to be offered to the vapor converter, the vapor converter heats up internal demineralized water through the heat of the vapor so as to generate secondary vapor, and the secondary vapor drives the vapor thermal compressor and the low temperature multi-effect sea water desalination system to generate fresh water. The system has the advantages that nuclear energy utilization is high in safety, the quality of generated fresh water is good, and electricity-water cogeneration is economic.

A system is configured to shield an interior chamber of a structure. The system may include a power source, an outer shield assembly operatively connected to the power source and coupled to an outer wall of the structure, and an inner shield assembly surrounding the internal chamber. The outer shield assembly generates a magnetic field through and around the structure. The inner shield assembly deflects radiation particles away from the interior chamber and re-directs portions of the magnetic field around the interior chamber.

The invention provides a nuclear energy and biomass energy association system method, and relates to the field of nuclear power. The nuclear energy and biomass energy association system comprises a nuclear energy subsystem and a biomass energy subsystem. The nuclear energy subsystem comprises a reactor, a high-temperature heat exchanger, a steam generator and a main pump, wherein the reactor, the high-temperature heat exchanger, the steam generator and the main pump are sequentially connected in an end-to-end mode; the main pump is connected with the reactor; the steam generator is sequentially connected with a steam turbine, a low-temperature heat exchanger, a condenser and a secondary circuit pump in an end-to-end mode. The biomass energy subsystem comprises a biomass gasification reactor, a washing tower, a reforming tower, a Fischer-Tropsch synthesis tower, a refining tower and a rectifying tower, wherein the biomass gasification reactor, the washing tower, the reforming tower, the Fischer-Tropsch synthesis tower, the refining tower and the rectifying tower are sequentially connected in an end-to-end mode; the high-temperature heat exchanger is connected with the reforming tower, and the low-temperature heat exchanger is connected with the refining tower; the steam generator generates steam to push the steam turbine to drive a generator to generate electricity. Nuclear energy subcycle and biomass energy subcycle are repeated, and a high temperature gas cooled reactor and biomass preparation liquid fuel are coupled through energy distribution. Clean electricity and liquid fuel can be generated, and the demand for integration of electricity and liquid fuel is met.

A system is configured to shield an interior chamber of a structure. The system may include a power source, an outer shield assembly operatively connected to the power source and coupled to an outer wall of the structure, and an inner shield assembly surrounding the internal chamber. The outer shield assembly generates a magnetic field through and around the structure. The inner shield assembly deflects radiation particles away from the interior chamber and re-directs portions of the magnetic field around the interior chamber.

The invention relates to a method of using nuclear power plant cooling tower waste heat to heat sea light raw water and reduce warm water discharge. The method is characterized in that a heat exchange system is disposed between a cooling tower and raw sea water, and two heat exchange tubes are disposed in the heat exchange system; the water inlet end of one heat exchange tube is communicated with the water outlet end of the cooling tower, and the water outlet end is communicated with the sea by a mixing pool, a water discharge open channel, and a tidal reach; the water inlet end of the other heat exchange tube is communicated with the raw sea water, and the water outlet end is communicated with a sea water desalination system. The method is advantageous in that by using the discharged water waste heat of the nuclear power plant cooling tower, the sea water desalination raw sea water temperature can be increased, and therefore the civil engineering and equipment investment can be reduced, the system operation power consumption can be reduced, the cooling tower discharged water waste heat can be further used, and the waste can be turned into the wealth; and at the same time, the water outlet temperature of the cooling tower can be reduced, and the ecotope of the tidal reach and the discharge sea area can be facilitated.

A hydrocarbon dehydrogenation process in which a hydrocarbon feed, normally a straight run naphtha, comprising acyclic and cyclic paraffins is dehydrogenated at elevated temperature of at least 540° C. with process heat provided at least in part by a solar or nuclear thermal energy source.

Provided are a nuclear energy and tower solar energy light-thermal combined power generation system and method. The system comprises a nuclear energy heating loop, a solar energy heating loop and a power generation loop. The power generation loop comprises a steam turbine connected with a power generator. A steam inlet of the steam turbine is connected with a steam generator through an overheater.A steam outlet of the steam turbine leads to the steam generator through a condenser and a water supply circulation pump. The nuclear energy heating loop is connected to the steam generator for heatexchange, and a main pump, a nuclear reactor and a voltage stabilizer are arranged in the nuclear energy heating loop. The solar energy heating loop is connected to the overheater for heat exchange, alow-temperature molten salt tank, a heat absorber and a high-temperature molten salt tank are arranged in the solar energy heating loop, and a heliostat field is matched with the heat absorber. Cooling water in the steam generator is heated into saturated steam by the nuclear energy heating loop to be fed into the overheater, and then the saturated steam in the overheater is heated into overheatsteam by the solar energy heating loop, so that the risk of solidification of molten salt is reduced, the factory power consumption is reduced, and the power generation efficiency is improved.

A prosthetic heart valve either of the mechanical type or the bio prosthetic type, comprises a tubular or cylindrical frame element, a plurality of injectors, a suturing member surrounding the tubular or cylindrical frame element, tether lines to secure the device during diastolic filling but more predominantly during systolic contraction that creates a vortex effect with externally supplied pressurized fluid injected angularly within a transport structure is provided. Such a unit is utilized to accelerate the hemodynamics, reduce the energy required for said transport or both. The annular frame is designed to allow a passageway for blood flow and regulating flow during systolic contraction. Such a result is achieved through the introduction of pressurized fluid (blood) via a plurality of injectors situated evenly around the circumference of the subject tubular or cylindrical unit, and angled uniformly for an even pressure injection of fluid within the conveyance component thereof.

The invention belongs to the technical field of pressurized water reactor nuclear power stations, and particularly relates to a heat-electricity-water combined system suitable for a large pressurized water reactor nuclear power unit and a production process. In the invention, a first nuclear power unit and a second nuclear power unit forms a nuclear steam supply system; a superheater, a steam generator, a deaerator, a secondary feed water heater, a primary feed water heater and a secondary water feeding pump form an industrial steam production system; a desalted water feeding pump, a water feeding tank, a desalted water facility, a seawater desalination facility, a heater, a first regulating valve, a second regulating valve, a seawater taking port, a seawater draining port, a standby fresh water taking port and a production water user form a seawater desalination and desalted water supply system; and a drainage pipeline returns to a pressurized water reactor nuclear power unit condenser through a third regulating valve and a fourth regulating valve to form a steam condensation water system. On the premise of ensuring nuclear safety, a nuclear power unit has the capabilities of producing industrial steam and producing fresh water through a seawater desalination technology.

A process for co-producing synthesis gas and power includes producing a synthesis gas comprising at least CO and H2 by reacting a hydrocarbonaceous feedstock with oxygen, the synthesis gas being at a first temperature, separating air from a compressed air stream by means of at least one ion transport membrane unit thereby producing a permeate stream consisting predominantly of oxygen and a reject stream of oxygen-depleted air at a second temperature which is lower than the first temperature, indirectly heating the reject stream of oxygen-depleted air with the synthesis gas and at least partially expanding, the heated reject stream of oxygen-depleted air through at least one turbine to generate power, producing an at least partially expanded reject stream of oxygen-depleted air, and feeding at least a portion of the permeate stream consisting predominantly of oxygen to the synthesis gas generation stage to provide oxygen for production of synthesis gas.

Heat from solar or nuclear heat sources is applied to provide at least a portion of the heat used in a cyclic petroleum refining process in which a hydrocarbon feedstream is contacted with a solid particulate contact material in a first step to treat the feedstream after which the solid contact material is separated or disengaged from the treated feedstream and regenerated in a separate regeneration zone before being returned to the first step for contact with additional feedstream. The entire cycle may be characterized as including an endothermic step, generally a reduction, and an exothermic step, generally an oxidation, with heat from the exothermic step being transferred from the exothermic step to the endothermic step by means of the circulating contact material. The application of the nuclear or solar heat may be applied to whichever step of the process requires heat from external sources. This technique may be applied to a method of regenerating catalysts and sorbents used in gas refining processes for removing contaminants from hydrocarbons and other gases including natural gas and syngas as well as to the FCC process.

The invention discloses a nuclear power plant waste heat utilization system and a nuclear power plant waste heat utilization method. The nuclear power plant waste heat utilization system comprises a first heat pump connected with a circulating water system in a nuclear power plant, a second heat pump connected with the first heat pump to form an intermediate circulating loop, and a steam-water heat exchanger; intermediate circulating water is output from the second heat pump, enters the first heat pump, exchanges heat with seawater in the first heat pump, is heated and returns to the second heat pump; the steam-water heat exchanger is connected with the second heat pump and heating heat exchange equipment to form a heating water circulation loop; and low-temperature water output by the heating heat exchange equipment enters the second heat pump and exchanges heat with intermediate circulating water, the low-temperature water enters the steam-water heat exchanger after being heated, andhigh-temperature water is formed and returns to the heating heat exchange equipment. Waste heat contained in circulating water of the nuclear power plant is effectively utilized, the energy comprehensive rate of the nuclear power plant is increased, the purposes of waste heat utilization and external clean heating of the nuclear power plant are achieved, and the environmental pollution problem caused by heating of a thermal power plant is reduced.

A prosthetic heart valve either of the mechanical type or the bio prosthetic type, comprises a tubular or cylindrical frame element, a plurality of injectors, a suturing member surrounding the tubular or cylindrical frame element, tether lines to secure the device during diastolic filling but more predominantly during systolic contraction that creates a vortex effect with externally supplied pressurized fluid injected angularly within a transport structure is provided. Such a unit is utilized to accelerate the hemodynamics, reduce the energy required for said transport or both. The annular frame is designed to allow a passageway for blood flow and regulating flow during systolic contraction. Such a result is achieved through the introduction of pressurized fluid (blood) via a plurality of injectors situated evenly around the circumference of the subject tubular or cylindrical unit, and angled uniformly for an even pressure injection of fluid within the conveyance component thereof.

A liquefied natural gas floating storage and regasification unit (LNG-FSRU) regasification system based on nuclear power comprises a steam generation module and an LNG gasification system, a nuclear reactor is arranged in a reactor cabin of the steam generation module and sequentially connected with a steam generator, the steam generator generates saturated steam of 40-80 bar, and the heat of the 40-80 bar saturated steam is provided for the power generation system, the pump set turbine system and the LNG gasification system. The LNG-FSRU regasification system applies heat energy generated by nuclear energy to a power generation system and a turbine system of a floating device and a propane and water glycol medium heating system based on a steam medium. Meanwhile, a nuclear power cooling system absorbs cold energy released by the regasification system. While saving energy and reducing emission, the seawater heat exchange load of the nuclear power cooling system can be greatly reduced, and the damage to the ecological environment is reduced from multiple angles. The system is stable, reliable, efficient in cold and hot energy utilization, energy-saving, environment-friendly and capable of reducing pollution.

The invention discloses a nuclear gas combined steam supply system which comprises a nuclear energy steam supply unit, a waste heat boiler, a heating and deoxidizing unit and a gas turbine generator set. The nuclear energy steam supply unit comprises a steam generator; the heating and deoxidizing unit is connected between the waste heat boiler and a water inlet of the steam generator; a superheater is arranged in the waste heat boiler; an inlet of the superheater is connected with a steam outlet of the steam generator; and the gas turbine generator set is connected with the waste heat boiler, so that flue gas formed after combustible gas is combusted is conveyed into the waste heat boiler. According to the nuclear gas combined steam supply system provided by the invention, the steam exhausted by the steam generator of a low-temperature reactor is heated through flue gas waste heat, so that the external steam supply temperature is increased; and meanwhile, the flue gas waste heat is used for preheating water supplied by the steam generator of the low-temperature reactor, so that nuclear heat energy is saved, and the total external steam supply amount is increased.

The invention is suitable for the technical field of nuclear heat supply, and provides a nuclear energy heat supply coupling biomass power station heat supply device which comprises a nuclear energy reactor and a bionic heat supply power station, wherein the nuclear energy reactor communicates with a heat supply system through a middle isolating loop, and is used for forming main heat supply; and the bionic heat supply power station communicates with the heat supply system, is coupled with the nuclear energy reactor and is used for forming auxiliary heat supply. In a heat supply season, the nuclear energy reactor is mainly responsible for heat supply, the bionic heat supply power station performs peak-adjusting through heat supply; in a non-heat-supply season, the nuclear energy reactor does not supply heat to the outside; and surplus nuclear energy is consumed by the bionic heat supply power station. The nuclear energy heat supply coupling biomass power station heat supply device improves utilization efficiency of nuclear heat supply, and improves the economical efficiency. A public system is deeply coupled to realize a three-in-one mode, so that the integral manufacturing cost and the occupied area of the equipment are reduced, operation stability is enhanced, and an equipment utilization rate is increased.

NUCLEAR STEAM SUPPLY SYSTEM AND METHOD This disclosure relates to a nuclear steam supply system, comprising: a nuclear power plant, a heat source circuit, a working fluid circuit, a steam consumer, and a steam heat accumulator, where the nuclear power plant is connected to the heat source circuit, the working fluid circuit is connected to the steam consumer and the steam heat accumulator, the steam heat accumulator is connected to the steam consumer, and the heat source circuit and the working fluid circuit are independent of each other. This disclosure allows for peak levelling load adjustment of the nuclear power plant and steam load adjustment of the steam consumer, while ensuring the operational safety of an electrical grid and a reactor. Summary figure: Fig. 1

A process (10) for co-producing synthesis gas and power includes in a synthesis gas generation stage (12), producing a synthesis gas (50) comprising at least CO and H2 by reacting a hydrocarbonaceous feedstock with oxygen, the synthesis gas being at a first temperature. Air is separated in an air separation stage (16) from a compressed air stream by means of at least one ion transport membrane unit (16.1 ) thereby producing a permeate stream (42) consisting predominantly of oxygen and a reject stream (44) of oxygen-depleted air at a second temperature which is lower than the first temperature. The reject stream (44) of oxygen-depleted air is heated indirectly with the synthesis gas (50) and at least partially expanded through at least one turbine (28) to generate power, producing an at least partially expanded reject stream of oxygen-depleted air (54). At least a portion of the permeate stream (42) consisting predominantly of oxygen is fed to the synthesis gas generation stage (12) to provide oxygen for production of synthesis gas.

The invention relates to the technical field of steam supply, and provides a high-low pressure steam coupling steam supply system and a control method thereof.The high-low pressure steam coupling steam supply system comprises a pressurized water reactor, flash evaporation equipment, an electric heat storage boiler, a pressure matcher and a data calculation control module; a multi-stage water-water heat exchange system is arranged between the pressurized water reactor and the flash evaporation equipment; the electric heat storage boiler is used for converting electricity into heat energy to be stored when green electricity generated by a wind power plant is excessive or electricity in a spot market is in a non-peak electricity price state, and heating feed water through the stored heat energy to generate high-pressure steam during steam supply; and the data calculation control module is used for enabling the steam at the outlet of the pressure matcher to meet the requirement of a steam supply user on the steam in a manner of inducing low-pressure steam by high-pressure steam based on parameters acquired by the nuclear energy side data instrument, the electric heat storage boiler side data instrument and the user side data instrument. While energy is saved and consumption is reduced, rapid development of the nuclear energy comprehensive utilization industry and the offshore wind power career is promoted.

The invention relates to a nuclear energy and slot-type solar-thermal combined power generation system and a power generation method. The nuclear energy and slot-type solar-thermal combined power generation system comprises a nuclear energy heating circuit, a solar heating circuit and a power generation circuit. The power generation circuit comprises a steam turbine connected with a generator, thesteam inlet of the steam turbine is connected with a steam generator through a superheater, and the steam outlet of the steam turbine is led into the steam generator through a condenser and a water supply circulating pump. The nuclear energy heating circuit is connected to the steam generator for heat exchange, and the nuclear energy heating circuit is provided with a main pump, a nuclear reactorand a voltage stabilizer. The solar heating circuit is connected to the superheater for heat exchange, and the solar heating circuit is provided with a low-temperature molten salt tank, a slot-type solar mirror field and a high-temperature molten salt tank. In the process of power generation, the nuclear energy heating circuit heats the cooling water in the steam generator into saturated steam, wherein the saturated steam is sent into the superheater; and the solar heating circuit heats the saturated steam in the superheater into superheated steam. According to the nuclear energy and slot-type solar-thermal combined power generation system and the power generation method, the risk of molten salt solidification can be reduced, the auxiliary power consumption can be reduced, and the power generation efficiency can be improved.

The invention discloses a method and a system for processing heavy soda ash by utilizing nuclear energy combined heat and power generation energy supply, and relates to the technical field of trona production. The method comprises the following steps: pretreating brine to obtain refined brine; carrying out steam stripping decomposition on the refined brine by using nuclear energy combined heat and power generation steam to obtain concentrated brine with Na2CO3 as a main component; the method comprises the following steps: carrying out multiple-effect evaporation on concentrated brine of which the main component is Na2CO3 by using nuclear energy combined heat and power generation steam, wherein Na2CO3 is separated out in a monohydrate sodium carbonate Na2CO3.H2O crystal form; carrying out centrifugal drying treatment on the monohydrate alkali crystal and the mother liquor by utilizing nuclear energy combined heat and power generation electric energy; and calcining the dried material by using nuclear energy combined heat and power generation steam to remove crystal water in the dried material, thereby obtaining the heavy sodium carbonate Na2CO3. According to the invention, the steam production quantity of the nuclear reactor is increased, and the steam power generation quantity of the nuclear reactor is correspondingly reduced, so that a large amount of energy loss generated when low-grade energy is converted into high-grade energy is reduced, and the overall efficiency is improved.

Nuclear energy integrated hydrocarbon operation systems include a well site having a subsurface hydrocarbon well configured to produce a produced water output. The system further includes a deployable nuclear reactor system configured to produce a heat output. The system may further include a deployable desalination unit configured to produce a desalinated water output using the produced water output of the subsurface hydrocarbon well and the heat output of the deployable nuclear reactor. The system may further include a deployable off-gas processing system configured to produce an industrial chemical using the off-gas output of the subsurface hydrocarbon well and the heat output of the deployable nuclear reactor.

The application discloses a method for estimating radioactivity concentration of desalinated water of a nuclear energy seawater desalination device, which comprises the following steps: firstly, according to the technological process of the nuclear energy thermal method seawater desalination device, the flowing direction of the medium and the migration direction of the radioactive substances are sorted out; then, according to the approach of the radioactive substances entering and removing in the intermediate loop fluid, the nuclide balance equation of the intermediate loop fluid is established, and then the radioactivity concentration calculation model of the intermediate loop water and the radioactivity concentration calculation model of the flash steam of the flash tank are obtained; then, according to the technological scheme of the MED device, the radioactivity concentration calculation model of the steam and the condensed water generated by each heat exchanger is established; then, the radioactivity level of the steam and the condensed water generated by each heat exchanger of the MED is calculated; finally, whether the desalinated water can meet the radioactivity control index is evaluated. The method can accurately calculate the radioactivity activity concentration of the desalinated water, and provides a reliable basis for the safety evaluation of the nuclear energy thermal method seawater desalination device.

The utility model discloses a modularized fused salt energy storage device for nuclear energy, which comprises a fused salt tank, a fused salt inlet pipe is arranged at the left side of the upper end of the fused salt tank, a salt inlet pipe is arranged at the lower end of the fused salt inlet pipe, and a fused salt outlet pipe is arranged at the left side of the upper end of the fused salt tank. The molten salt pump comprises a molten salt outlet pipe, a molten salt pump motor is installed at the upper end of the molten salt outlet pipe, a salt outlet pipe is installed at the lower end of the molten salt outlet pipe, a molten salt pump body is installed at the lower end of the salt outlet pipe, and the outer wall of the molten salt outlet pipe is sleeved with a sleeve. Cooling water is added into the casing pipe through the water inlet in the upper end position of the casing pipe, and the cooling water circulates at the spiral pipe in the casing pipe and is in full contact with the molten salt outlet pipe, so that the temperature of the molten salt outlet pipe can be reduced, overheating is prevented, and the interface is protected from being damaged.

Nuclear energy integrated hydrocarbon operation systems include a well site having a subsurface hydrocarbon well configured to produce a produced water output. The system further includes a deployable nuclear reactor system configured to produce a heat output. The system may further include a deployable desalination unit configured to produce a desalinated water output using the produced water output of the subsurface hydrocarbon well and the heat output of the deployable nuclear reactor. The system may further include a deployable off-gas processing system configured to produce an industrial chemical using the off-gas output of the subsurface hydrocarbon well and the heat output of the deployable nuclear reactor.

The invention relates to heat power engineering, in particular, to methods that use a working medium for producing useful work from heat of an external source. The method comprises interaction of the working medium with an energy source and interaction of the working medium with an additional low-temperature energy source in the form of the positron state of the Dirac's matter by means of bringing the working medium into quantum-mechanical resonance with said state. The quantum-mechanical resonance is initiated by changing at least one of the thermodynamic parameters of the working medium, while the value of spontaneous fluctuations of the variable parameter in the vicinity of the line of absolute instability in the state diagram of the working medium is predetermined, and the change step for the thermodynamic parameter is set to be lower than the predetermined value of said fluctuations.

This specification describes techniques that can be implemented in an integrated energy system (IES) for producing nitric acid (HNO3) while minimizing the carbon footprint. When implemented by a resource production plant, such techniques may include receiving electricity and steam from a power plant and producing hydrogen (H2) gas from the steam in a hydrogen (H2) production subplant; receiving electricity from a power plant and air from the environment and producing nitrogen (N2) gas in a nitrogen (N2) production subplant; producing ammonia (NH3) from hydrogen (H2) gas and nitrogen (N2) gas in a nitrogen production subplant; and producing nitric acid (HNO3) from ammonia (NH3) in a nitric acid (HNO3) production subplant.