CN106098122A - A kind of nuclear power generating system based on supercritical carbon dioxide Brayton cycle - Google Patents

A kind of nuclear power generating system based on supercritical carbon dioxide Brayton cycle Download PDF

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Publication number
CN106098122A
CN106098122A CN201610378017.XA CN201610378017A CN106098122A CN 106098122 A CN106098122 A CN 106098122A CN 201610378017 A CN201610378017 A CN 201610378017A CN 106098122 A CN106098122 A CN 106098122A
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China
Prior art keywords
carbon dioxide
supercritical carbon
gas
cycle
precooler
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CN201610378017.XA
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廖吉香
张海
郑群
刘兴业
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Harbin Engineering University
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Harbin Engineering University
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)

Abstract

The invention belongs to energy-conserving and environment-protective field, be specifically related to a kind of nuclear power generating system based on supercritical carbon dioxide Brayton cycle.A kind of nuclear power generating system based on supercritical carbon dioxide Brayton cycle, including the recompression circulation of supercritical carbon dioxide Bretton and Trans-critical cycle carbonoxide Rankine cycle, the recompression circulation of supercritical carbon dioxide Bretton includes nuclear reactor, turbine, 2 compressors, cryogenic regenerator, high temperature regenerator and 7 parts of precooler.The present invention, under operating condition, can utilize the character of its real gas to reduce work done during compression etc., use CO2It is not required to the highest can have suitable efficiency with circulated helium as the temperature needed for the circulation of working medium.

Description

A kind of nuclear power generating system based on supercritical carbon dioxide Brayton cycle
Technical field
The invention belongs to energy-conserving and environment-protective field, be specifically related to a kind of nuclear energy based on supercritical carbon dioxide Brayton cycle Electricity generation system.
Background technology
Along with energy growing tension, renewable energy power generation technology is utilized to be increasingly subject to pay attention to.In new forms of energy, as the 4th For candidate's heap-type of nuclear power system, very high temperature gas cooled reactor and gas cooled fast reactor have the features such as high security, high efficiency, purposes are wide, And all intend using helium as reactor direct circulation working medium.Owing to helium has stable, nontoxic, without artificial radioactivity, thermal capacitance The feature such as big, therefore, HTGR the most in the world is widely used helium as the working medium of direct Closed Brayton Power Cycle and anti- Answer the coolant of heap.But circulated helium needs higher maximum cycle temperature (core exit temperature) to can be only achieved satisfied efficiency, Therefore, the structural material of reactor, fuel element material etc. are proposed higher requirement, simultaneously because helium density is low, can The shortcomings such as coefficient of compressibility is little, the manufacture of circulated helium turbomachine also creates certain difficulty.
Compared with helium, CO2Because its density is big, and it is prone to compression, CO2Critical temperature be 304.19K, compare ambient temperature Slightly higher, critical pressure is 7.3773MPa, under operating condition, the character of its real gas can be utilized to reduce work done during compression etc., use CO2It is not required to the highest can have suitable efficiency with circulated helium as the temperature needed for the circulation of working medium, therefore, uses CO2Make Working medium for HTGR circulation has wide potentiality.Meanwhile, CO2Circulate the most recommended being used in Gen-IV nuclear energy system Sodium-cooled fast reactor (SFR) and Lead cooled fast breeder reactor (LFR).
Summary of the invention
It is an object of the invention to provide a kind of can be used in power industry follow based on supercritical carbon dioxide Bretton The nuclear power generating system of ring.
The object of the present invention is achieved like this:
A kind of nuclear power generating system based on supercritical carbon dioxide Brayton cycle, including supercritical carbon dioxide mine-laying Recompression of pausing circulates and Trans-critical cycle carbonoxide Rankine cycle, and the recompression circulation of supercritical carbon dioxide Bretton includes nuclear reaction Heap, turbine, 2 compressors, cryogenic regenerator, high temperature regenerator and 7 parts of precooler；Trans-critical cycle carbonoxide Rankine cycle bag Include turbine, booster pump, 4 parts of precooler；The recompression circulation of supercritical carbon dioxide Bretton is a part of CO2Gas passes through Stage compressor is compressed into high pressure, is preheated to split-compressor outlet temperature, and and split-compressor in cryogenic regenerator The CO of outlet2Gas mixes；Mixed CO2Gas continues to heat in high temperature regenerator, is then passed through nuclear reactor and is heated To maximum cycle temperature；The supercritical CO of high temperature2Gas enters turbine expansion acting, exports electricity, afterwards CO2Gas exists respectively Heat exchange in high temperature regenerator and cryogenic regenerator；CO through cryogenic regenerator2Gas distribution, a part of CO2Gas is two grades of pressures Contracting machine compresses, another part CO2Gas cools down in precooler；And the heat that precooler 1 now discharges, it is used for heating CO in the Rankine cycle of bottom2, it is heated to form supercriticality, enters turbine expansion acting and generate electricity, from turbine out Exhaust steam enters in condenser and condenses, then completes bottom subsystem power generation cycle after the boosting of intensified pump in entrance precooler 1.
The beneficial effects of the present invention is: the present invention, under operating condition, can utilize the character of its real gas to reduce pressure Contracting merits etc., use CO2It is not required to the highest can have suitable efficiency with circulated helium as the temperature needed for the circulation of working medium.
Accompanying drawing explanation
Fig. 1 nuclear power generating system based on supercritical carbon dioxide Brayton cycle.
Detailed description of the invention
Below in conjunction with the accompanying drawings the present invention is described further.
Electricity generation system of the present invention includes mainly including two parts, and a part is followed for the recompression of supercritical carbon dioxide Bretton Ring, this circulation is main loop；Another part be Trans-critical cycle carbonoxide Rankine cycle as bottoming cycle for reclaiming precooler Waste heat, thus improve the efficiency of whole electricity generation system.Major cycle include nuclear reactor, turbine, 2 compressors, cryogenic regenerator, High temperature regenerator and 7 critical pieces of precooler (1 and 2)；Bottoming cycle includes turbine, booster pump, (1) 4 main portion of precooler Part.Major cycle process is a part of CO2Gas is compressed into high pressure by stage compressor, is preheated to two in cryogenic regenerator Stage compressor outlet temperature, and the CO exported with split-compressor2Gas mixes；Mixed CO2Gas continues in high temperature backheat Device heats, is then passed through nuclear reactor and is heated to maximum cycle temperature；The supercritical CO of high temperature2Gas enters turbine expansion Acting, exports electricity, afterwards CO2Gas heat exchange in high temperature regenerator and cryogenic regenerator respectively；Through cryogenic regenerator CO2Gas distribution, a part of CO2Gas compresses in split-compressor, another part CO2Gas cools down in precooler.And now The heat that discharges of precooler 1, may be used for the CO in heated base Rankine cycle2, it is heated to form supercriticality, so The acting of rear entrance turbine expansion generates electricity, and enters condenser from turbine exhaust steam out and condenses, then after the boosting of intensified pump Enter and precooler 1 completes bottom subsystem power generation cycle.
As it is shown in figure 1, nuclear power generating system main device based on supercritical carbon dioxide Brayton cycle has nuclear reaction Heap (11), turbine power generation unit (1) (2), stage compressor (3) and split-compressor (4), precooler 1 (5), precooler 2 (6), High temperature regenerator (7), cryogenic regenerator (8), booster pump (9) and condenser (10).Electromotor is connected to form with turbine engine Turbine power generation unit (1) (2), pipeline, adnexa and detection that it is connected in also including system and control device, fill in major cycle It is equipped with nuclear reactor (11), turbine power generation unit (1), stage compressor (3) and split-compressor (4), precooler 1 (5), pre-cooling Device 2 (6), high temperature regenerator (7), cryogenic regenerator (8) are sequentially connected with, and bottom cycle has turbine power generation unit (2), precooler 1 (5), booster pump (9) and condenser (10) are sequentially connected with.Major cycle technological process is a part of CO2Gas passes through stage compressor (3) made its temperature, pressure raise by compression, cryogenic regenerator is preheated to the outlet temperature of split-compressor (4), and with two The CO that level compressor (3) exports2Gas mixes；Mixed CO2Gas continues to enter core after (7) heating in high temperature regenerator Reactor (11) so that it is become the supercritical fluid of high pressure, the supercritical CO of high pressure2Enter turbine power generation unit (1) expansion to do Merit generates electricity, thus nuclear energy is converted into electric energy, supercritical CO2Temperature reduces after pressure reduces at high-temperature heat-exchanging (7) and low temperature In regenerator (8), heat exchange cooling, is now still supercriticality, then through cryogenic regenerator CO2Gas distribution, one Divide CO2Gas compresses in split-compressor and makes its temperature and pressure raise；Another part CO2Gas cools down in precooler.And this Time the heat that discharges of precooler 1, may be used for the CO in heated base Rankine cycle2, it is heated to form supercriticality, Then drive turbine power generation unit (2) generating, enter condenser (10) from turbine exhaust steam out and be condensed into liquid, then Enter after intensified pump (9) boosting in precooler 1 and complete bottom subsystem power generation cycle.Nuclear reactor (11) can use direct-type Heating, it is possible to use indirect type heating, mini-channel tube high-performance heat exchanger can be used.Booster pump (9) uses multi-stage diaphragm pump.Thoroughly Flat generating set (1) main shaft is connected with split-compressor (4) and stage compressor (3) main shaft.

Claims (1)

1. a nuclear power generating system based on supercritical carbon dioxide Brayton cycle, including supercritical carbon dioxide Bretton Recompression circulation and Trans-critical cycle carbonoxide Rankine cycle, it is characterised in that: supercritical carbon dioxide Bretton recompression circulation bag Include nuclear reactor, turbine, 2 compressors, cryogenic regenerator, high temperature regenerator and 7 parts of precooler；Trans-critical cycle carbonoxide is bright Willing circulation includes turbine, booster pump, 4 parts of precooler；The recompression circulation of supercritical carbon dioxide Bretton is a part of CO2 Gas is compressed into high pressure by stage compressor, is preheated to split-compressor outlet temperature in cryogenic regenerator, and with two The CO of stage compressor outlet2Gas mixes；Mixed CO2Gas continues to heat in high temperature regenerator, is then passed through nuclear reaction Heap is heated to maximum cycle temperature；The supercritical CO of high temperature2Gas enters turbine expansion acting, exports electricity, afterwards CO2Gas Body heat exchange in high temperature regenerator and cryogenic regenerator respectively；CO through cryogenic regenerator2Gas distribution, a part of CO2Gas Split-compressor compresses, another part CO2Gas cools down in precooler；And the heat that precooler 1 now discharges, CO in heated base Rankine cycle2, it is heated to form supercriticality, enters turbine expansion acting and generate electricity, from thoroughly The exhaust steam cleared enters in condenser and condenses, then completes bottom subsystem generating after the boosting of intensified pump in entrance precooler 1 Circulation.
CN201610378017.XA 2016-05-31 2016-05-31 A kind of nuclear power generating system based on supercritical carbon dioxide Brayton cycle Pending CN106098122A (en)

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Cited By (16)

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CN106677849A (en) * 2016-12-29 2017-05-17 中科瑞华原子能源技术有限公司 Liquid heavy metal cooling reactor electricity generating device adopting supercritical CO2 working medium
CN108257701A (en) * 2017-12-11 2018-07-06 清华大学 The power regulating method and device of high temperature gas cooled reactor coupling enclosed Bradenton cycle
CN108361163A (en) * 2017-12-05 2018-08-03 北京石油化工学院 Electricity generation system
CN108868930A (en) * 2018-06-07 2018-11-23 江苏科技大学 Overcritical/critical-cross carbon dioxide association circulating power generation system that afterheat of IC engine utilizes
CN109524141A (en) * 2018-10-16 2019-03-26 中广核研究院有限公司 Seawater desalination system and its small-sized powered by nuclear energy output device and power output method
CN109616229A (en) * 2019-01-11 2019-04-12 哈尔滨电气股份有限公司 Step heat supply supercritical carbon dioxide circulating thermoelectric co-feeding system for sodium-cooled fast reactor
CN109869292A (en) * 2019-03-04 2019-06-11 西安交通大学 It is a kind of using carbon dioxide as the middle low-temperature heat source/underground heat energy-storing and power-generating system and method for working medium
CN110030048A (en) * 2019-04-28 2019-07-19 三峡大学 A kind of S-CO2Recycle the nuclear power generating system combined with ORC circulation and heat circulation method
CN110863961A (en) * 2019-11-28 2020-03-06 西安石油大学 Supercritical CO2Recompression brayton and LNG combined cycle power generation system
CN110905747A (en) * 2019-11-28 2020-03-24 西安石油大学 Combined power cycle power generation system utilizing high-temperature solar energy and LNG cold energy
CN111105883A (en) * 2019-12-31 2020-05-05 中国核动力研究设计院 Heat pipe reactor system with supercritical carbon dioxide as thermoelectric conversion working medium
CN111724917A (en) * 2020-07-17 2020-09-29 中国工程物理研究院核物理与化学研究所 Heat pipe stack coupling supercritical CO2Cyclic nuclear power plant and method of use
CN111968764A (en) * 2020-08-22 2020-11-20 西安交通大学 Liquid nuclear fuel heat pipe reactor power supply system and method for recompression Brayton cycle
CN113027551A (en) * 2021-04-13 2021-06-25 西安交通大学 Mobile integrated double-process gas-cooled reactor system and working method thereof
CN113086945A (en) * 2021-04-14 2021-07-09 中核能源科技有限公司 High-temperature gas cooled reactor hydrogen-electricity-water heat cogeneration system
CN113819671A (en) * 2021-10-21 2021-12-21 湖南大学 Carbon dioxide-based power generation and refrigeration combined system

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Cited By (23)

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Publication number Priority date Publication date Assignee Title
CN106677849A (en) * 2016-12-29 2017-05-17 中科瑞华原子能源技术有限公司 Liquid heavy metal cooling reactor electricity generating device adopting supercritical CO2 working medium
CN108361163A (en) * 2017-12-05 2018-08-03 北京石油化工学院 Electricity generation system
CN108361163B (en) * 2017-12-05 2023-10-13 北京石油化工学院 Power generation system
CN108257701A (en) * 2017-12-11 2018-07-06 清华大学 The power regulating method and device of high temperature gas cooled reactor coupling enclosed Bradenton cycle
CN108257701B (en) * 2017-12-11 2020-11-03 清华大学 Power adjusting method for high-temperature gas cooled reactor coupled closed Brayton cycle
CN108868930A (en) * 2018-06-07 2018-11-23 江苏科技大学 Overcritical/critical-cross carbon dioxide association circulating power generation system that afterheat of IC engine utilizes
CN108868930B (en) * 2018-06-07 2020-07-14 江苏科技大学 Supercritical/transcritical carbon dioxide combined cycle power generation system utilizing waste heat of internal combustion engine
CN109524141A (en) * 2018-10-16 2019-03-26 中广核研究院有限公司 Seawater desalination system and its small-sized powered by nuclear energy output device and power output method
CN109616229A (en) * 2019-01-11 2019-04-12 哈尔滨电气股份有限公司 Step heat supply supercritical carbon dioxide circulating thermoelectric co-feeding system for sodium-cooled fast reactor
CN109869292A (en) * 2019-03-04 2019-06-11 西安交通大学 It is a kind of using carbon dioxide as the middle low-temperature heat source/underground heat energy-storing and power-generating system and method for working medium
CN110030048B (en) * 2019-04-28 2024-03-12 三峡大学 S-CO 2 Nuclear power generation system combining cycle and ORC cycle and thermal energy cycle method
CN110030048A (en) * 2019-04-28 2019-07-19 三峡大学 A kind of S-CO2Recycle the nuclear power generating system combined with ORC circulation and heat circulation method
CN110905747A (en) * 2019-11-28 2020-03-24 西安石油大学 Combined power cycle power generation system utilizing high-temperature solar energy and LNG cold energy
CN110863961A (en) * 2019-11-28 2020-03-06 西安石油大学 Supercritical CO2Recompression brayton and LNG combined cycle power generation system
CN110905747B (en) * 2019-11-28 2021-07-13 西安石油大学 Combined power cycle power generation system utilizing high-temperature solar energy and LNG cold energy
CN111105883A (en) * 2019-12-31 2020-05-05 中国核动力研究设计院 Heat pipe reactor system with supercritical carbon dioxide as thermoelectric conversion working medium
CN111105883B (en) * 2019-12-31 2022-04-19 中国核动力研究设计院 Heat pipe reactor system with supercritical carbon dioxide as thermoelectric conversion working medium
CN111724917A (en) * 2020-07-17 2020-09-29 中国工程物理研究院核物理与化学研究所 Heat pipe stack coupling supercritical CO2Cyclic nuclear power plant and method of use
CN111968764A (en) * 2020-08-22 2020-11-20 西安交通大学 Liquid nuclear fuel heat pipe reactor power supply system and method for recompression Brayton cycle
CN113027551A (en) * 2021-04-13 2021-06-25 西安交通大学 Mobile integrated double-process gas-cooled reactor system and working method thereof
CN113086945A (en) * 2021-04-14 2021-07-09 中核能源科技有限公司 High-temperature gas cooled reactor hydrogen-electricity-water heat cogeneration system
CN113819671A (en) * 2021-10-21 2021-12-21 湖南大学 Carbon dioxide-based power generation and refrigeration combined system
CN113819671B (en) * 2021-10-21 2022-12-27 湖南大学 Power generation and refrigeration combined system based on carbon dioxide

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