CN115274170B - Nuclear reactor system for high-thermal-efficiency Brayton and Rankine combined cycle power generation - Google Patents

Nuclear reactor system for high-thermal-efficiency Brayton and Rankine combined cycle power generation Download PDF

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CN115274170B
CN115274170B CN202210916774.3A CN202210916774A CN115274170B CN 115274170 B CN115274170 B CN 115274170B CN 202210916774 A CN202210916774 A CN 202210916774A CN 115274170 B CN115274170 B CN 115274170B
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heat
steam
temperature
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working medium
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CN115274170A (en
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夏庚磊
卢帅杰
周涛
张博文
王晨阳
张元东
孙觊琳
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Harbin Engineering University
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Harbin Engineering University
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04Reactor and engine not structurally combined
    • G21D5/08Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • G21D5/12Liquid working medium vaporised by reactor coolant
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01KSTEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K11/00Plants characterised by the engines being structurally combined with boilers or condensers
    • F01K11/02Plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01KSTEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K23/00Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids
    • F01K23/02Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids the engine cycles being thermally coupled
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01KSTEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K25/00Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for
    • F01K25/08Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours
    • F01K25/10Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours the vapours being cold, e.g. ammonia, carbon dioxide, ether
    • F01K25/103Carbon dioxide
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

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  • Chemical & Material Sciences (AREA)
  • General Engineering & Computer Science (AREA)
  • Combustion & Propulsion (AREA)
  • Mechanical Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)

Abstract

The invention discloses a nuclear reactor system for high-heat-efficiency Brayton and Rankine combined cycle power generation, which comprises a nuclear reactor, wherein the nuclear reactor is communicated with a heat exchange device for heat exchange, a first loop and a second loop are communicated with the heat exchange device, a first working medium flows in the first loop, a second working medium flows in the second loop, wherein the first working medium led out of the heat exchange device sequentially passes through a first heat recovery device, a steam generation device, a second heat recovery device and a third heat recovery device after being subjected to work by the first power generation device, and then is led into a gas compression device, and the first working medium at the air outlet end of the gas compression device passes through the second heat recovery device and the first heat recovery device for heat absorption and then is led into the heat exchange device. According to the invention, a precooler is not specially arranged in the Brayton cycle, the temperature of a working medium at the inlet of a compressor is reduced, the Brayton efficiency is improved, the initial parameters of the inlet of a steam turbine can be improved, the Rankine cycle efficiency is further improved, and the total thermal efficiency of the system is further improved.

Description

Nuclear reactor system for high-thermal-efficiency Brayton and Rankine combined cycle power generation
Technical Field
The invention relates to the technical field of nuclear reactor engineering, in particular to a nuclear reactor system for high-heat-efficiency Brayton and Rankine combined cycle power generation.
Background
The combined cycle is a two-loop or three-loop cycle scheme, so that the cascade utilization of a high-temperature heat source of a high-primary parameter reactor can be realized, the Brayton cycle can fully utilize the quality of reactor energy, the Rankine cycle can utilize the quantity of the reactor energy, and the Brayton turbine and the steam turbine can drive a generator to output power to the outside at the same time. The combined cycle has great advantages for the high initial parameter reactor, and can ensure higher cycle efficiency.
The existing Brayton and Rankine combined cycle design is divided into a pre-cooling design and a non-pre-cooling design, wherein the inlet temperature of a compressor is low, the power consumption of the compressor is low, the Brayton cycle efficiency is high, and the defects are that the precooler directly brings the Brayton cycle heat energy out of a cycle system, so that the Rankine cycle efficiency is reduced; the result is the contrary in the design of no precooling, namely the compressor inlet temperature is higher, and the compressor power consumption is great, and brayton cycle inefficiency, and brayton cycle heat energy can't directly take circulation system out, and rankine cycle efficiency is high.
In the existing combined cycle design, the reheating of the waste heat boiler is generally designed between the high pressure cylinder and the low pressure cylinder of the steam turbine, but the most important purpose of the reheating mode is to improve the dryness of the inlet of the low pressure cylinder, and the cycle heat efficiency cannot be improved necessarily. Therefore, how to reduce the inlet temperature of the compressor to the maximum extent and improve the initial inlet parameters of the Rankine cycle turbine without arranging a precooler, thereby improving the total heat efficiency of the system is a problem which needs to be solved by the person skilled in the art.
Disclosure of Invention
The invention aims to provide a nuclear reactor system for generating electricity by combining high-heat-efficiency Brayton and Rankine cycle, which solves the problems in the prior art, can realize that a precooler is not specially arranged in the Brayton cycle, reduces the temperature of a working medium at an inlet of a compressor, improves the Brayton cycle efficiency, can improve the primary parameters of an inlet of a steam turbine, further improves the Rankine cycle efficiency, and further improves the total heat efficiency of the system. In order to achieve the above object, the present invention provides the following solutions: the invention provides a nuclear reactor system for high-heat-efficiency Brayton and Rankine combined cycle power generation, which comprises a nuclear reactor, wherein the nuclear reactor is communicated with a heat exchange device for heat exchange, the heat exchange device is communicated with a first loop and a second loop, a first working medium flows in the first loop, a second working medium flows in the second loop,
the first working medium led out of the heat exchange device sequentially passes through a first heat recovery device, a steam generation device, a second heat recovery device and a third heat recovery device after doing work, and then is led into the gas compression device, the first working medium at the gas outlet end of the gas compression device passes through the second heat recovery device and the first heat recovery device to absorb heat and then is led into the heat exchange device, the first circuit is provided with a first power generation device, and the first working medium passes through the first power generation device and then enters the first heat recovery device;
the second working medium led out by the heat exchange device is led into the second power generation device, the second working medium at the low-temperature steam outlet end of the second power generation device is condensed and pressurized and then passes through the third heat recovery device, the steam extraction heat recovery device and the steam generation device to absorb heat and then is led into the heat exchange device, and the second working medium at the high-temperature steam outlet end of the second power generation device is led into the steam extraction heat recovery device to release heat.
Preferably, the heat exchange device is a high-temperature heat exchanger, the first heat regenerator is a first heat regenerator, the second heat regenerator is a second heat regenerator, the third heat regenerator is a third heat regenerator, the steam generator is a steam generator, and the gas compression device is a compressor;
the high-temperature outlet and the low-temperature inlet of the nuclear reactor are respectively communicated with the high-temperature heat exchanger through pipelines, a high-temperature outlet of the high-temperature heat exchanger is communicated with the high-temperature inlet of the first heat regenerator through a pipeline, the low-temperature outlet of the first heat regenerator is communicated with the high-temperature inlet of the steam generator through a pipeline, the low-temperature outlet of the steam generator is communicated with the high-temperature inlet of the second heat regenerator through a pipeline, the low-temperature outlet of the second heat regenerator is communicated with the high-temperature inlet of the third heat regenerator through a pipeline, the low-temperature outlet of the third heat regenerator is communicated with the air inlet of the compressor through a pipeline, the air outlet of the compressor is communicated with the low-temperature inlet of the second heat regenerator through a pipeline, the high-temperature outlet of the second heat regenerator is communicated with the low-temperature inlet of the first heat regenerator through a pipeline.
Preferably, the first power generation device comprises a brayton turbine, the air inlet end of the brayton turbine is communicated with a high-temperature outlet of the high-temperature heat exchanger through a pipeline, the air outlet end of the brayton turbine is communicated with a high-temperature inlet of the first heat regenerator through a pipeline, and a first power generator is connected to the brayton turbine in a transmission mode.
Preferably, the compressor, the brayton turbine and the first generator are coaxially arranged.
Preferably, the steam extraction and heat recovery device is a steam extraction and heat recovery combination, the second power generation device comprises a steam turbine, the other high-temperature outlet of the high-temperature heat exchanger is communicated with the steam inlet end of the steam turbine through a pipeline, the low-temperature steam outlet end of the steam turbine is communicated with the low-temperature inlet of the third heat regenerator after being condensed through a pipeline, the low-temperature outlet of the third heat regenerator is communicated with the steam extraction and heat recovery combination liquid inlet end through a pipeline, and the high-temperature steam outlet end of the steam turbine is communicated with the steam extraction and heat recovery combination steam inlet end through a pipeline.
Preferably, the steam turbine is in transmission connection with a second generator, and is provided with two steam outlets, wherein the low-temperature steam outlet of the steam turbine is communicated with a condenser steam inlet end through a pipeline, the condenser liquid outlet end is communicated with the low-temperature inlet of the third heat regenerator, and the high-temperature steam outlet of the steam turbine is communicated with the steam extraction and heat recovery combined steam inlet end.
Preferably, the steam extraction and regeneration combination comprises at least one steam extraction heat exchanger.
Preferably, the first working medium is supercritical carbon dioxide, and the second working medium is steam.
The invention discloses the following technical effects:
1. according to the invention, the pre-cooler is not specially arranged in the Brayton cycle, so that the reduction of the inlet temperature of the gas compression device is realized, the heat energy is prevented from being directly taken out of the circulation system, the thermal efficiency of the Brayton cycle is improved, and the reduction of the Rankine cycle efficiency is avoided.
2. Compared with reheating of a traditional combined cycle waste heat boiler, primary parameters of an inlet of the second power generation device can be reheated, the average heat absorption temperature of the Rankine cycle can be improved from the source, and the Rankine cycle efficiency is improved.
3. The second heat recovery device and the third heat recovery device are arranged to reduce the temperature of the inlet of the gas compression device, and meanwhile, the working medium at the outlet of the gas compression device and the Rankine cycle condensate water can be primarily heated, so that low-temperature heat energy is further recovered, and the heat efficiency of the system is improved.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions of the prior art, the drawings that are needed in the embodiments will be briefly described below, it being obvious that the drawings in the following description are only some embodiments of the present invention, and that other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic diagram of a connection relationship of a combined cycle power generation system;
the system comprises a 1-nuclear reactor, a 2-high temperature heat exchanger, a 3-first heat regenerator, a 4-steam generator, a 5-steam extraction heat regeneration combination, a 6-second heat regenerator, a 7-third heat regenerator, an 8-compressor, a 9-Brayton turbine, a 10-first generator, an 11-steam turbine, a 12-second generator, a 13-condenser and a 14-water pump.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
In order that the above-recited objects, features and advantages of the present invention will become more readily apparent, a more particular description of the invention will be rendered by reference to the appended drawings and appended detailed description.
Referring to fig. 1, the invention provides a nuclear reactor system for combined cycle power generation with high thermal efficiency, which comprises a nuclear reactor 1, wherein the nuclear reactor 1 is communicated with a heat exchange device for heat exchange, the heat exchange device is communicated with a first loop and a second loop, a first working medium circulates in the first loop, a second working medium circulates in the second loop, wherein the first working medium led out of the heat exchange device sequentially passes through a first heat recovery device, a steam generation device, a second heat recovery device and a third heat recovery device after being subjected to power generation by the first power generation device, and is led into a gas compression device after being subjected to heat release by the third heat recovery device, the first working medium at the gas outlet end of the gas compression device passes through the second heat recovery device and the first heat recovery device for heat absorption and is led into the heat exchange device, the first loop is provided with the first power generation device, and the first working medium enters the first heat recovery device through the first power generation device; and the second working medium led out by the heat exchange device is led into the second power generation device, condensed and pressurized at the low-temperature steam outlet end of the second power generation device, and then led into the heat exchange device after being absorbed by the third heat recovery device, the steam extraction heat recovery device and the steam generation device, and the second working medium at the high-temperature steam outlet end of the second power generation device is led into the steam extraction heat recovery device to release heat.
The first loop is matched with the second loop, heat generated by the nuclear reactor 1 is utilized to do work, after the nuclear reactor 1 exchanges heat with the heat exchange device, the temperature of the heat exchange device is increased, and the heat exchange device is used for heating the first working medium and the second working medium.
In the first loop, after the first working medium works and generates electricity through the first power generation device, the generated exhaust gas enters the first heat recovery device to release heat once, the first working medium after heat release is completed enters the steam generation device to release heat twice, then enters the second heat recovery device to release heat three times, finally enters the third heat recovery device to release heat four times, the temperature of the first working medium is obviously reduced after the first working medium releases heat four times, the first working medium after heat four times is introduced into the gas compression device, pressurized through the gas compression device, enters the second heat recovery device to absorb heat once, then enters the first heat recovery device to absorb heat twice, and the first working medium after heat absorption and temperature rise twice enters the heat exchange device to exchange heat with the heat exchange device to obtain the first working medium meeting the power generation requirement. In the process, in the second heat recovery device and the first heat recovery device, the boosted first working medium exchanges heat with the first working medium before boosting, so that on one hand, the temperature of gas entering the gas compression device is reduced, the power consumption of the compressor is reduced, and on the other hand, the temperature of the gas entering the heat exchange device is increased, so that the heat exchange device can output high-temperature first working medium rapidly and further recover low-temperature heat energy, and the heat efficiency of the system is improved.
In the second loop, the second working medium enters a second power generation device to do work and generate power, and the second working medium is divided into two paths: and after the heat exchange is finished, the heated liquid is guided into a steam generating device by the steam extraction and heat recovery device, absorbs heat and converts the liquid into steam in the steam generating device, and finally is led into the heat exchange device. In the process, part of steam of the second power generation device is introduced into the steam extraction and heat recovery device, the part of steam heats liquid after primary temperature rise, meanwhile, the part of steam is condensed into liquid after heat release, and the condensed liquid is mixed with liquid after secondary temperature rise and then enters the steam generation device for vaporization.
Wherein the first working medium is a Brayton cycle working medium, and the second working medium is a Rankine cycle working medium.
The nuclear reactor 1 is one of a molten salt reactor, a lead bismuth reactor or a lead cold fast reactor, or other reactors which can provide a large amount of heat.
Further, a pipe is communicated between the nuclear reactor 1 and the heat exchange device, and a coolant, which is optionally but not limited to lead bismuth, lead or molten salt, is arranged in the pipe, absorbs heat in the nuclear reactor 1 through the coolant, conveys the coolant into the heat exchange device to release heat, and guides heat generated by the nuclear reactor 1 into the heat exchange device through the circulation of the coolant.
In a further optimized scheme, the heat exchange device is a high-temperature heat exchanger 2, the first heat regenerator is a first heat regenerator 3, the second heat regenerator is a second heat regenerator 6, the third heat regenerator is a third heat regenerator 7, the steam generator is a steam generator 4, and the gas compressor is a compressor 8; the high-temperature outlet and the low-temperature inlet of the nuclear reactor 1 are respectively communicated with the high-temperature heat exchanger 2 through pipelines, the high-temperature outlet of the high-temperature heat exchanger 2 is communicated with the high-temperature inlet of the first heat regenerator 3 through a pipeline, the low-temperature outlet of the first heat regenerator 3 is communicated with the high-temperature inlet of the steam generator 4 through a pipeline, the low-temperature outlet of the steam generator 4 is communicated with the high-temperature inlet of the second heat regenerator 6 through a pipeline, the low-temperature outlet of the second heat regenerator 6 is communicated with the high-temperature inlet of the third heat regenerator 7 through a pipeline, the low-temperature outlet of the third heat regenerator 7 is communicated with the air inlet end of the compressor 8 through a pipeline, the air outlet end of the compressor 8 is communicated with the low-temperature inlet of the second heat regenerator 6 through a pipeline, the high-temperature outlet of the second heat regenerator 6 is communicated with the low-temperature inlet of the first heat regenerator 3 through a pipeline, and the high-temperature outlet of the first heat regenerator 3 is communicated with the low-temperature inlet of the high-temperature heat exchanger 2 through a pipeline.
The second working medium subjected to secondary heating enters the steam generator 4, and as the first working medium releases heat secondarily in the steam generator 4, the heat released by the part is used for heating the second working medium, and the second working medium is vaporized and then enters the high-temperature heat exchanger 2.
The first heat regenerator 3, the second heat regenerator 6 and the third heat regenerator 7 are respectively provided with a high-temperature inlet, a low-temperature outlet, a low-temperature inlet and a high-temperature outlet, wherein the high-temperature inlet and the low-temperature outlet are communicated through pipelines, the low-temperature inlet and the high-temperature outlet are communicated through another pipeline, a first working medium before pressurization and a first working medium after pressurization are respectively circulated in the two pipelines in the first heat regenerator 3 and the second heat regenerator 6, and a first working medium before pressurization and a second working medium in a liquid state are respectively circulated in the two pipelines in the third heat regenerator 7. Through the arrangement, heat exchange between the first working medium before pressurization and the first working medium after pressurization is realized in the first heat regenerator 3 and the second heat regenerator 6, and heat exchange between the first working medium before pressurization and the second working medium in a liquid state is realized in the third heat regenerator 7.
The first heat regenerator 3 and the second heat regenerator 6 are partition wall type heat exchangers or printed circuit board type heat exchangers, and the third heat regenerator 7 is a partition wall type heat exchanger.
Wherein the steam generator 4 is preferably, but not limited to, a once-through steam generator.
Further optimizing scheme, first power generation facility includes brayton turbine 9, and brayton turbine 9 air inlet end passes through pipeline and a high temperature export intercommunication of high temperature heat exchanger 2, and brayton turbine 9 air outlet end passes through pipeline and a regenerator 3 high temperature import intercommunication, and the transmission is connected with first generator 10 on the brayton turbine 9. The first working medium is directly connected into the Brayton turbine 9 after being heated by the high-temperature heat exchanger 2, and the generated exhaust steam is led into the first heat regenerator 3 for heat release after the Brayton turbine 9 performs work.
The brayton turbine 9 is in turn a brayton turbine which is used to convert the energy contained in the first working medium into mechanical energy by means of a rotating impeller. The first working medium with energy converts the energy into kinetic energy when passing through the spray pipe, and impacts the blades when flowing through the impeller to push the impeller to rotate, thereby driving the turbine shaft to rotate and outputting mechanical work, the mechanical work is transmitted with the first generator 10, and the first generator 10 generates electricity.
Further optimizing scheme, compressor 8, brayton turbine 9, first generator 10 coaxial arrangement. The above three are coaxially arranged, namely, after the first working medium is introduced into the brayton turbine 9, the turbine shaft of the brayton turbine 9 is driven to rotate, the turbine shaft is coaxially arranged with the rotating shaft of the compressor 8 and the rotating shaft of the first generator 10, and the turbine shaft can drive the compressor 8 to rotate in sequence, so that the compressor 8 works normally, no additional power supply is needed, and the turbine shaft drives the rotating shaft of the first generator 10 to rotate, thereby being convenient for the first generator 10 to generate electricity.
According to a further optimized scheme, the steam extraction and regeneration device is a steam extraction and regeneration combination 5, the second power generation device comprises a steam turbine 11, the other high-temperature outlet of the high-temperature heat exchanger 2 is communicated with the steam inlet end of the steam turbine 11 through a pipeline, the steam turbine 11 is provided with two steam outlets, exhaust steam with different temperatures is respectively led out, the low-temperature steam outlet end of the steam turbine 11 is communicated with the steam inlet end of a condenser 13 through a pipeline, the liquid outlet end of the condenser 13 is communicated with an inlet communicating pipe of a water pump 14, the outlet of the water pump 14 is communicated with the low-temperature inlet of a third heat regenerator 7, the low-temperature outlet of the third heat regenerator 7 is communicated with the liquid inlet end of the steam extraction and regeneration combination 5 through a pipeline, and the high-temperature steam outlet end of the steam turbine 11 is communicated with the air inlet end of the steam extraction and regeneration combination 5 through a pipeline. After the second working medium enters the steam turbine 11, part of steam is fully used for acting, exhaust steam after acting is condensed into liquid, the condensed liquid is introduced into the third heat regenerator 7 to absorb heat for primary heating, and then enters the steam extraction heat recovery combination 5 to absorb heat for secondary heating, in the process, another part of steam enters the steam extraction heat recovery combination 5 through an air extraction loop pipeline under the action of a steam extraction device (not shown in the figure) after initially acting, and the part of steam carries out secondary heating on the liquid subjected to primary heating. At the same time, the part of the steam is condensed into liquid after heat dissipation and is mixed with the liquid after the secondary temperature rise, and finally the liquid is led into the steam generator 4 for temperature rise and vaporization.
The steam turbine 11 is a multi-cylinder steam turbine, and a steam-water separation device is arranged between the high pressure cylinder and the low pressure cylinder.
According to a further optimization scheme, a second generator 12 is connected to the steam turbine 11 in a transmission manner, the steam turbine 11 is provided with two steam outlets, wherein the low-temperature steam outlet of the steam turbine 11 is communicated with the steam inlet end of the condenser 13 through a pipeline, the liquid outlet end of the condenser 13 is communicated with the low-temperature inlet of the third heat regenerator 7, and the high-temperature steam outlet of the steam turbine 11 is communicated with the steam inlet end of the steam extraction heat regeneration combination 5. The two steam outlets of the second generator 12 respectively guide out the exhaust steam with different temperatures, wherein one part of the exhaust steam enters the condenser 13 and is condensed into liquid under the action of the condenser 13, and the other part of the exhaust steam enters the steam extraction and heat recovery combination 5.
The working medium for absorbing heat of the second working medium in the condenser 13 may be one or a combination of several of seawater, fresh water or air, and may be other working medium, so that it is preferable to absorb heat of the second working medium.
Wherein the steam turbine 11 is coaxially disposed with the second generator 12 so that the second generator 12 normally generates electricity.
Further, a water pump 14 is arranged on a pipeline of the condenser 13 communicated with the third heat regenerator 7, and the water pump 14 is used for introducing condensed liquid into the third heat regenerator 7.
Further optimizing scheme, the steam extraction and regeneration combination 5 comprises at least one steam extraction heat exchanger. The extraction heat exchanger may be provided in plurality to re-exchange heat and condense the steam extracted by the steam turbine 11.
The steam extraction heat exchanger is optionally a surface heat exchanger or a hybrid heat exchanger or a combination of two types of heat exchangers, and another water pump (not shown in the figure) is arranged in the heat exchanger combination and is used for leading the water which is heated secondarily and mixed into the steam generator 4.
In a further optimized scheme, the first working medium is supercritical carbon dioxide, and the second working medium is steam.
Specifically, when power generation is performed, heat generated by the nuclear reactor 1 is led into the high-temperature heat exchanger 2 through a medium, the high-temperature heat exchanger heats supercritical carbon dioxide of a first working medium and steam of a second working medium, in a first loop, the first working medium performs work and power generation through the brayton turbine 9, generated exhaust gas enters the first heat regenerator 3 to perform primary heat release, the first working medium after heat release is completed enters the steam generator 4 to perform secondary heat release, then enters the second heat regenerator 6 to perform tertiary heat release, finally enters the third heat regenerator 7 to perform quaternary heat release, the temperature of the first working medium is obviously reduced after the first working medium is subjected to quaternary heat release, the first working medium after the fourth heat release is led into the compressor 8, the first working medium after the first working medium is pressurized by the compressor 8, enters the third heat regenerator 7 to perform primary heat absorption, then enters the first heat regenerator 3 to perform secondary heat absorption, the first working medium after the two heat increases, and the first working medium after the two heat increases temperature enters the high-temperature heat exchanger 2 to perform heat exchange with the high-temperature heat exchanger 2 to derive the first working medium meeting the power generation requirement.
In the second loop, the second working medium enters the steam turbine 11 to do work and generate electricity, after passing through the steam turbine 11, part of the second working medium fully does work, waste steam with lower temperature is formed and then is introduced into the condenser 13 to be condensed into liquid, after being condensed into liquid, the liquid is pressurized by the water pump 14 and then enters the third heat regenerator 7 to be heated once, then enters the steam extraction heat regeneration combination 5 to be heated twice, after the heating of the second time is finished, the heated liquid is introduced into the steam generator 4 by the steam extraction heat regeneration combination 5, the liquid absorbs heat and is converted into gas in the steam generator 4 and finally is introduced into the high-temperature heat exchanger 2, the other part of the second working medium initially does work, under the action of the steam extraction device, the part of the second working medium is initially done and then is extracted out of the steam turbine 11, the part of the second working medium is introduced into the steam extraction combination 5 to be heated twice, meanwhile, the part of the second working medium is cooled and then condensed into the liquid, and the second working medium condensed into the liquid is mixed and then introduced into the steam generator 4.
In the description of the present invention, it should be understood that the terms "longitudinal," "transverse," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like indicate or are based on the orientation or positional relationship shown in the drawings, merely to facilitate description of the present invention, and do not indicate or imply that the devices or elements referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus should not be construed as limiting the present invention.
The above embodiments are only illustrative of the preferred embodiments of the present invention and are not intended to limit the scope of the present invention, and various modifications and improvements made by those skilled in the art to the technical solutions of the present invention should fall within the protection scope defined by the claims of the present invention without departing from the design spirit of the present invention.

Claims (6)

1. A nuclear reactor system for high thermal efficiency brayton and rankine combined cycle power generation, comprising a nuclear reactor (1), characterized in that: the nuclear reactor (1) is communicated with a heat exchange device for heat exchange, a first loop and a second loop are communicated with the heat exchange device, a first working medium flows in the first loop, a second working medium flows in the second loop, wherein,
the first working medium led out of the heat exchange device sequentially passes through a first heat recovery device, a steam generation device, a second heat recovery device and a third heat recovery device after doing work, and then is led into the gas compression device, and the first working medium at the gas outlet end of the gas compression device passes through the second heat recovery device and the first heat recovery device to absorb heat and then is led into the heat exchange device;
the second working medium led out of the heat exchange device is led into a second power generation device, condensed and pressurized by the second working medium at the low-temperature steam outlet end of the second power generation device, absorbed by the third heat recovery device, the steam extraction heat recovery device and the steam generation device and then led into the heat exchange device, and the second working medium at the high-temperature steam outlet end of the second power generation device is led into the steam extraction heat recovery device to release heat;
the heat exchange device is a high-temperature heat exchanger (2), the first heat recovery device is a first heat recovery device (3), the second heat recovery device is a second heat recovery device (6), the third heat recovery device is a third heat recovery device (7), the steam generation device is a steam generator (4), and the gas compression device is a compressor (8);
the high-temperature outlet and the low-temperature inlet of the nuclear reactor (1) are respectively communicated with the high-temperature heat exchanger (2) through pipelines, a high-temperature outlet of the high-temperature heat exchanger (2) is communicated with a high-temperature inlet of the first heat regenerator (3) through a pipeline, a low-temperature outlet of the first heat regenerator (3) is communicated with a high-temperature inlet of the steam generator (4) through a pipeline, a low-temperature outlet of the steam generator (4) is communicated with a high-temperature inlet of the second heat regenerator (6) through a pipeline, a low-temperature outlet of the second heat regenerator (6) is communicated with a high-temperature inlet of the third heat regenerator (7) through a pipeline, a low-temperature outlet of the third heat regenerator (7) is communicated with an air inlet end of the compressor (8) through a pipeline, an air outlet end of the compressor (8) is communicated with a low-temperature inlet of the second heat regenerator (6) through a pipeline, a high-temperature outlet of the second heat regenerator (6) is communicated with a low-temperature inlet of the first heat regenerator (3) through a pipeline, and a high-temperature outlet of the first heat regenerator (3) is communicated with a high-temperature inlet of the third heat regenerator (7) through a pipeline;
the first working medium is supercritical carbon dioxide, and the second working medium is steam.
2. The high thermal efficiency brayton and rankine combined cycle power generating nuclear reactor system of claim 1, wherein: the first power generation device comprises a Brayton turbine (9), the air inlet end of the Brayton turbine (9) is communicated with a high-temperature outlet of the high-temperature heat exchanger (2) through a pipeline, the air outlet end of the Brayton turbine (9) is communicated with a high-temperature inlet of the first heat regenerator (3) through a pipeline, and a first power generator (10) is connected to the Brayton turbine (9) in a transmission manner.
3. The high thermal efficiency brayton and rankine combined cycle power generating nuclear reactor system of claim 2, wherein: the compressor (8), the Brayton turbine (9) and the first generator (10) are coaxially arranged.
4. The high thermal efficiency brayton and rankine combined cycle power generating nuclear reactor system of claim 1, wherein: the steam extraction and heat recovery device is a steam extraction and heat recovery combination (5), the second power generation device comprises a steam turbine (11), the other high-temperature outlet of the high-temperature heat exchanger (2) is communicated with the steam inlet end of the steam turbine (11), the low-temperature steam outlet end of the steam turbine (11) is communicated with the low-temperature inlet of the third heat regenerator (7) after being condensed by the pipeline, the low-temperature outlet of the third heat regenerator (7) is communicated with the liquid inlet end of the steam extraction and heat recovery combination (5) by the pipeline, and the high-temperature steam outlet end of the steam turbine (11) is communicated with the steam inlet end of the steam extraction and heat recovery combination (5) by the pipeline.
5. The high thermal efficiency brayton and rankine combined cycle power generating nuclear reactor system of claim 4, wherein: the steam turbine (11) is connected with a second generator (12) in a transmission way, the steam turbine (11) is provided with two steam outlets, the low-temperature steam outlet of the steam turbine (11) is communicated with a steam inlet end of a condenser (13) through a pipeline, a liquid outlet end of the condenser (13) is communicated with a low-temperature inlet of the third heat regenerator (7), and the high-temperature steam outlet of the steam turbine (11) is communicated with the steam inlet end of the steam extraction and heat regeneration combination (5).
6. The high thermal efficiency brayton and rankine combined cycle power generating nuclear reactor system of claim 4, wherein: the steam extraction and regeneration combination (5) comprises at least one steam extraction heat exchanger.
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