34results 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.

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.

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.

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.

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 an industrial steam production system for a pressurized water reactor nuclear power unit. The system comprises: a nuclear steam supply device, which is a pressurized water reactor nuclear power unit used for supplying heat source steam to an industrial steam production device while generating power; the industrial steam production device, an inlet of which is connected withan outlet of the nuclear steam supply device, wherein heat source steam exchanges heat with feed water introduced into the industrial steam production device, and the feed water is heated by the heatsource steam to generate industrial steam with preset parameters to be conveyed to a heat user. According to the invention, the pressurized water reactor nuclear power unit is used as a support, secondary loop main steam of the pressurized water reactor nuclear power unit is used for producing industrial steam through an industrial steam production device, the steam is conveyed to a user througha steam pipe network, thus realizing the application of externally supplying clean industrial steam by the nuclear power station, developing a new way for comprehensive utilization of nuclear energy,effectively solving the environmental pollution caused by traditional energy sources like coal, improving the energy structure, guaranteeing the industrial development steam demand, and improving theeconomic benefits of the nuclear power station.

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.

The invention relates to the technical field of coupling steam supply systems, in particular to a nuclear energy and photoelectricity coupling steam supply system. The nuclear energy and photoelectricity coupling steam supply system comprises a reactor, a first heat exchanger and a steam demand end, wherein a head pipeline is connected with the reactor and the reactor side of the first heat exchanger, and a reactor coolant pump is arranged on a coolant cold section of the head pipeline to form a first loop; the nuclear energy and photoelectricity coupling steam supply system further comprises a second heat exchanger, wherein the reactor side of the second heat exchanger is connected with the steam side of the first heat exchanger through an intermediate loop pipeline to form a second loop, an intermediate loop circulating pump is arranged on an intermediate loop cold section of the intermediate loop pipeline, and a heat exchange section of a tail pipeline is located on the steam side in the second heat exchanger; a water inlet section of the tail pipeline is connected with a water supply system, and a low-temperature steam output section of the tail pipeline is connected with the steam demand end to form a third loop. According to the nuclear energy and photoelectricity coupling steam supply system, compared with the prior art, coupling steam supply of the nuclear energy and the new energy is achieved; the second loop is added to isolate leakage of a reactor coolant loop, so that the situation that radioactivity of the first loop leaks to a user side is avoided.

The invention discloses a multivariant combined supply integrated nuclear reactor system, comprising a nuclear reactor, a sea water desalination module, a fresh water storage tower, a group or multiple groups of energy conversion and supply terminals, and an energy output regulator, wherein the energy output regulator is used for preferentially distributing the energy provided by the nuclear reactor to a group or multiple groups of energy conversion and supply terminals; the sea water desalination module is a power balance part, and used for applying the rest energy after distribution to generate fresh water; the fresh water storage tower is used for storing fresh water generated from the sea water desalination module, wherein the output power of the nuclear reactor is maintained at a constant level; a group or multiple groups of energy conversion and supply terminals perform the power adjustment on the energy demand side. As the energy source, the nuclear reactor improves the stability and persistence of the energy supply, and has good adjusting flexibility; the energy fluctuation is transferred to the storable fresh water resource.

The heat removal and recovery systems of a nuclear energy source and the heat requirements of a nearby industrial facility are designed to achieve zero or near-zero greenhouse gas emissions from the industrial facility. Alternative arrangements of heat loops or belts to and from the nuclear heat source and within the industrial facility utilize heat exchange equipment at the interfaces and replace the use of fired furnaces and boilers. Technologies and processes can be selected to avoid the need or use of all or most of the furnaces and boilers. The design scheme applies to both new and existing retrofitted industrial facilities.