CN112484011A - Nuclear power station two-loop thermodynamic system and using method thereof - Google Patents

Nuclear power station two-loop thermodynamic system and using method thereof Download PDF

Info

Publication number
CN112484011A
CN112484011A CN202011469157.0A CN202011469157A CN112484011A CN 112484011 A CN112484011 A CN 112484011A CN 202011469157 A CN202011469157 A CN 202011469157A CN 112484011 A CN112484011 A CN 112484011A
Authority
CN
China
Prior art keywords
heat
nuclear power
pressure heater
pipeline
heating
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN202011469157.0A
Other languages
Chinese (zh)
Inventor
赵清森
张鼎
任天翔
王加勇
邓德兵
陈伟
杨杰
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China General Nuclear Power Corp
CGN Power Co Ltd
Suzhou Nuclear Power Research Institute Co Ltd
Original Assignee
China General Nuclear Power Corp
CGN Power Co Ltd
Suzhou Nuclear Power Research Institute Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China General Nuclear Power Corp, CGN Power Co Ltd, Suzhou Nuclear Power Research Institute Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN202011469157.0A priority Critical patent/CN112484011A/en
Publication of CN112484011A publication Critical patent/CN112484011A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22DPREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
    • F22D1/00Feed-water heaters, i.e. economisers or like preheaters
    • F22D1/003Feed-water heater systems
    • 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
    • F01K7/00Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating
    • F01K7/34Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being of extraction or non-condensing type; Use of steam for feed-water heating
    • F01K7/38Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being of extraction or non-condensing type; Use of steam for feed-water heating the engines being of turbine type
    • 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
    • F01K7/00Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating
    • F01K7/34Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being of extraction or non-condensing type; Use of steam for feed-water heating
    • F01K7/40Use of two or more feed-water heaters in series
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22DPREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
    • F22D1/00Feed-water heaters, i.e. economisers or like preheaters
    • F22D1/32Feed-water heaters, i.e. economisers or like preheaters arranged to be heated by steam, e.g. bled from turbines
    • F22D1/325Schematic arrangements or control devices therefor
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22DPREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
    • F22D1/00Feed-water heaters, i.e. economisers or like preheaters
    • F22D1/50Feed-water heaters, i.e. economisers or like preheaters incorporating thermal de-aeration of feed-water
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F24HEATING; RANGES; VENTILATING
    • F24SSOLAR HEAT COLLECTORS; SOLAR HEAT SYSTEMS
    • F24S23/00Arrangements for concentrating solar-rays for solar heat collectors
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F24HEATING; RANGES; VENTILATING
    • F24SSOLAR HEAT COLLECTORS; SOLAR HEAT SYSTEMS
    • F24S50/00Arrangements for controlling solar heat collectors
    • F24S50/80Arrangements for controlling solar heat collectors for controlling collection or absorption of solar radiation
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • G21D1/02Arrangements of auxiliary equipment
    • 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
    • Y02E10/00Energy generation through renewable energy sources
    • Y02E10/40Solar thermal energy, e.g. solar towers
    • Y02E10/44Heat exchange systems
    • 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

Landscapes

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

Abstract

The invention relates to a two-loop thermodynamic system of a nuclear power station and a use method thereof, wherein the two-loop thermodynamic system comprises a heat exchange pipeline connected between a condenser and an evaporator, a low-pressure heat recovery system for heating condensed water in the heat exchange pipeline, a high-pressure heat recovery system and a deaerator, and also comprises a heating system, wherein the heating system comprises a heat generating device and a heat collecting and exchanging device for heating the condensed water in the heat exchange pipeline by using heat generated by the heat generating device; according to the invention, the water supply of the nuclear power station is heated by using solar energy, the use of a secondary loop thermodynamic system of the nuclear power station for steam extraction is reduced on the premise of not using external energy, the working quality of main steam is improved particularly in summer, the power generation power of a power station is finally improved, and meanwhile, the application of the solar energy in the nuclear power station provides a new way for the subsequent optimization of nuclear power safe operation.

Description

Nuclear power station two-loop thermodynamic system and using method thereof
Technical Field
The invention relates to the field of solar photo-thermal utilization and nuclear power, in particular to a two-loop thermodynamic system of a nuclear power station and a using method thereof.
Background
At present, a secondary loop thermodynamic system of a nuclear power station heats the feed water temperature by extracting working steam in a steam turbine, so that the overall thermal efficiency of the nuclear power station is improved. The two-loop thermodynamic system comprises a low-pressure heat regenerative system, a deaerator and a high-pressure heat regenerative system, after a steam turbine works, condensed water generated by the condenser is heated by the low-pressure heat regenerative system, enters the deaerator for high-temperature deaerating, is further heated by the high-pressure heat regenerative system, and then enters a boiler (the boiler generates steam and then supplies the steam to the steam turbine again for power generation).
Solar energy is an inexhaustible clean energy, and in today with increasingly severe environmental and energy problems, many countries have studied and practiced solar power generation technology and achieved some achievements. Solar photo-thermal power generation is also called focusing solar photo-thermal power generation, can utilize solar energy on a large scale, and is an effective way for solving the energy problem. The solar radiation energy is collected by an optical system and is used for heating a working medium to generate high-temperature steam to drive a steam turbine set to generate power. Solar photo-thermal power generation is an effective mode for utilizing solar energy, and currently, the solar photo-thermal power generation mainly comprises a plurality of typical solar power generation modes such as a groove type solar power generation mode, a tower type solar power generation mode, a linear Fresnel type solar power generation mode and a disc type solar power generation mode. Due to the intermittency and the fluctuation of solar energy resources, the simple Fresnel type thermal power generation system has the problems of unstable output power and the like. To realize stable and continuous operation, a heat storage device is generally required, but the addition of the heat storage device can increase the manufacturing cost of the solar thermal power generation system.
The solar nuclear power generating set is also used as clean energy, the power generating principle is similar, and how to complement the solar energy and the nuclear energy to improve the generating efficiency of the nuclear power generating set in summer is a small challenge.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provide a two-loop thermodynamic system of a nuclear power station.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
the utility model provides a two return circuits thermodynamic system of nuclear power station, two return circuits thermodynamic system is including connecting the heat transfer pipeline between condenser and evaporimeter, carry out the low pressure backheat system that heats to the condensate water in the heat transfer pipeline, high pressure backheat system, the oxygen-eliminating device, low pressure backheat system includes the low pressure jar, locate No. 1 low pressure heater on the heat transfer pipeline, No. 2 low pressure heater, No. 3 low pressure heater, No. 4 low pressure heater, high pressure backheat system includes the high pressure jar, locate No. 6 high pressure heater on the heat transfer pipeline, No. 7 high pressure heater, two return circuits thermodynamic system still includes heating system, heating system includes heat generating device, the heat collection heat transfer device who makes the heat that heat generating device produced the condensate water in the heat transfer pipeline.
Preferably, the heat generating device is a solar photo-thermal device.
Preferably, the solar photothermal device comprises a linear fresnel reflective concentrating system.
Preferably, the heating system further comprises a heating pipeline, two ends of the heating pipeline are respectively communicated with the heat exchange pipeline, and the heat collection and exchange device is arranged on the heating pipeline.
Preferably, the heating system further comprises a bypass pipeline, two ends of which are respectively communicated with the heat exchange pipeline, and the bypass pipeline is connected with the heating pipeline in parallel.
Preferably, the heat collection and exchange device is arranged at the downstream of any one of No. 1 low-pressure heater, No. 2 low-pressure heater, No. 3 low-pressure heater, No. 4 low-pressure heater, No. 6 high-pressure heater and No. 7 high-pressure heater.
Preferably, the heat collection and exchange device is arranged at the downstream of the No. 4 low-pressure heater.
Preferably, the heat collection and exchange device is arranged at the downstream of the No. 7 high-pressure heater.
Preferably, the bypass pipeline is provided with a first switching valve; two second switching valves are arranged on the heating pipeline and are respectively positioned at the upstream and the downstream of the heat collection and exchange device.
The invention also relates to a using method of the nuclear power station secondary loop thermodynamic system, when the linear Fresnel reflection light-gathering system can receive solar radiation energy, the first switching valve is closed, the second switching valve is opened, or the first switching valve and the second switching valve are both opened; when the linear Fresnel reflection condensation system cannot receive solar radiation energy, the first switching valve is opened, and the second switching valve is closed.
Due to the implementation of the technical scheme, compared with the prior art, the invention has the following advantages:
according to the invention, the water supply of the nuclear power station is heated by using solar energy, the use of a secondary loop thermodynamic system of the nuclear power station for steam extraction is reduced on the premise of not using external energy, the working quality of main steam is improved particularly in summer, the power generation power of a power station is finally improved, and meanwhile, the application of the solar energy in the nuclear power station provides a new way for the subsequent optimization of nuclear power safe operation.
Drawings
FIG. 1 is a schematic view of the overall layout of a two-loop thermodynamic system (a heat collecting and exchanging device is arranged at the outlet of a low-pressure heat regenerative system) according to the present invention;
FIG. 2 is a schematic view of the overall layout of a two-loop thermodynamic system (a heat collecting and exchanging device is arranged at the outlet of a high-pressure heat regenerative system) according to the present invention;
wherein: 100. a condenser; 200. an evaporator; 300. a heat exchange conduit; 40. a deaerator; 50. a linear Fresnel reflection light-condensing system; 51. a heat collection and exchange device; g1, low pressure cylinder; g2, high pressure cylinder; j1, low pressure heater No. 1; j2, low pressure heater No. 2; j3, low pressure heater No. 3; j4, low pressure heater No. 4; j6, high pressure heater No. 6; j7, high pressure heater No. 7; d1, a bypass line; d2, heating the pipeline; f1, a first switching valve; f2, and a second switching valve.
Detailed Description
The invention is described in further detail below with reference to the figures and specific examples.
As shown in fig. 1 and 2, a two-loop thermodynamic system of a nuclear power plant includes a heat exchange pipe 300 connected between a condenser 100 and an evaporator 200, a low-pressure regenerative system for heating condensed water in the heat exchange pipe 300, a high-pressure regenerative system, and a deaerator 40, where the low-pressure regenerative system includes a low-pressure cylinder g1, a No. 1 low-pressure heater j1, a No. 2 low-pressure heater j2, a No. 3 low-pressure heater j3, and a No. 4 low-pressure heater j4, the high-pressure regenerative system includes a high-pressure cylinder g2, a No. 6 high-pressure heater j6 and a No. 7 high-pressure heater j7, which are disposed on the heat exchange pipe 300, and the two-loop thermodynamic system further includes a heating system, which includes a heat generating device, and a heat collecting and exchanging device 51 for heating the condensed water in the heat exchange pipe 300 by the heat generated by the heat generating device.
The heat generating device is a solar photo-thermal device. The solar photothermal device includes a linear fresnel reflective concentrating system 50. By utilizing the unique characteristics of the solar photothermal technology, the reflecting mirror group of the linear Fresnel reflection condensing system 50 is arranged on the factory area of the nuclear power station or the roof of a steam turbine machine room, the energy gathered by the solar photothermal device is directly used for heating the water supply of the two-loop thermodynamic system of the nuclear power station through the heat collection and exchange device 51, the water supply temperature is increased, the steam is pumped by the steam turbine regenerative system, the pumped steam is returned to the steam turbine for continuous work, and the heat efficiency and the economical efficiency of the nuclear power station are improved.
In order to improve the light and heat collecting efficiency, the reflecting condenser mirror surface is designed to be a secondary song surface type with the light condensing characteristic, and the optical light condensing efficiency is more than or equal to 90 percent. The surface coating of the heat collection and exchange device 51 is an improvement of a solar selective absorption coating, can resist the high temperature of 300 ℃, and has the absorption rate of over 96 percent in the solar spectrum range.
In addition, the invention adopts a single-shaft automatic tracking system, so that the linear Fresnel reflection light-gathering system 50 can collect solar radiation energy with maximum efficiency in different seasons and different sunshine periods, and the control mode can select preset process control or photoelectric sensing control. The preset process control is to calculate the position and angle of the reflector according to the solar operation rule and control the rotation of the mirror shaft through the movement of the mechanical mechanism. The photoelectric sensing control is that the photoelectric sensor instantly collects and measures the sunlight direction, and the mechanical mechanism is controlled to move after the sunlight direction is processed by a circuit. The disadvantage of the photoelectric sensing control mode is that the correct position of the sun cannot be found in cloudy or rainy days, and manual intervention and adjustment are needed.
The heat collection and heat exchange device 51 can be arranged at the downstream of any one of the low-pressure heater j1 No. 1, the low-pressure heater j2 No. 2, the low-pressure heater j3 No. 3, the low-pressure heater j4 No. 4, the high-pressure heater j6 No. 6 and the high-pressure heater j7 No. 7, and the heating efficiency of the heat collection and heat exchange device 51 is higher as the heat collection and heat exchange device is closer to the outlet of the heat exchange pipeline 300; in this embodiment, due to the limitation of the field space of the existing two-circuit regenerative system, the heat collecting and exchanging device 51 is preferably disposed downstream of the No. 4 low-pressure heater j4 or downstream of the No. 7 high-pressure heater j7 without being greatly modified on the field.
If the heating system heats the final water supply temperature of the two-loop regenerative system (downstream of the No. 7 high-pressure heater j 7), the yield is the highest, the steam extraction amount of the low-pressure heater, the deaerator 40 and the high-pressure heater is reduced, or the low-pressure heater, the deaerator 40 and the high-pressure heater are not used for heating at all, and the use of steam extraction is also avoided. If the heating system is used for heating condensed water at the outlet of the low-pressure heater (the downstream of the No. 4 low-pressure heater j4 (the upstream of the deaerator 40), the steam extraction amount of the deaerator 40 and the high-pressure heater is reduced, the extracted steam of the exhaust heat recovery system returns to the steam turbine to continue acting, the power and the heat efficiency of the unit are improved, the comprehensive efficiency is lower than that of a mode for heating the outlet temperature of the high-pressure heater in the mode, automatic control is easy to realize, and the potential safety hazard caused by the fact that the final water supply temperature is over-poor.
The heating system further comprises a heating pipeline d2 with two ends respectively communicated with the heat exchange pipeline 300, and the heat collection and exchange device 51 is arranged on the heating pipeline d 2. In addition, the heating system further includes a bypass pipe d1 having both ends respectively communicated with the heat exchange pipe 300, and the bypass pipe d1 is disposed in parallel with the heating pipe d 2. The bypass pipeline d1 is provided with a first switching valve f 1; two second switching valves f2 are arranged on the heating pipeline d2, and the two second switching valves f2 are respectively positioned at the upstream and the downstream of the heat collecting and exchanging device 51.
The invention also relates to a use method of the nuclear power plant two-loop thermodynamic system, when the linear Fresnel reflection light-gathering system 50 can receive solar radiation energy (for example, in the daytime), the first switching valve f1 is closed, the second switching valve f2 is opened, or the first switching valve f1 and the second switching valve f2 are both opened; when the linear fresnel reflection concentrating system 50 is unable to receive solar radiation energy (e.g., at night), the first switching valve f1 is opened and the second switching valve f2 is closed.
The final feed water temperature control deviation of a nuclear power plant M310 unit commonly used in China is 226 +/-2.5 ℃, the control deviation needs to be switched and used through a bypass pipeline d1 and a heating pipeline d2, and the maximum deviation is always controlled not to exceed 2.5 ℃ under the condition of solar radiation energy change, so that the operation safety of key equipment of the nuclear power plant is guaranteed.
The bypass pipe d1 is used for shunting the flow of the condensed water of the heat collection and heat exchange device 51 during heat exchange, and also controlling the water outlet temperature of the heat exchange pipe 300, so that the feed water discharged from the heating pipe d2 after heat exchange of the heat collection and heat exchange device 51 is prevented from vaporizing by mixing cold water and hot water. In addition, the distance between the final feed water temperature of the nuclear power station and a design value is not more than 2.5 ℃ at most, and the thermal power of a heating thermal system is not more than 17MW at most according to thermal balance calculation. According to a conservative concept in the nuclear power field, 10% of safety allowance is designed, so that the maximum designed thermal power of the heating system does not exceed 15 MW; the thermal power of the heating system is actually determined according to the temperature and the pressure of the condensed water at the outlet of the heater, so that the condensed water is prevented from being vaporized to cause equipment damage.
In conclusion, the invention utilizes the solar energy to heat the nuclear power station feed water, reduces the use of the secondary loop thermodynamic system of the nuclear power station for steam extraction on the premise of not depending on external energy, particularly improves the working quality of the main steam in summer, finally improves the power generation power of the power station, and simultaneously provides a new way for the subsequent optimization of nuclear power safe operation by the application of the solar energy in the nuclear power station.
The above embodiments are merely illustrative of the technical concept and features of the present invention, and the purpose thereof is to enable those skilled in the art to understand the content of the present invention and implement the invention, and not to limit the scope of the invention, and all equivalent changes or modifications made according to the spirit of the present invention should be covered by the scope of the present invention.

Claims (10)

1. The utility model provides a two return circuits thermodynamic system of nuclear power station, two return circuits thermodynamic system is including connecting the heat transfer pipeline between condenser and evaporimeter, the low pressure backheat system, high pressure backheat system, the oxygen-eliminating device that heat is carried out to the condensate water in the heat transfer pipeline, the low pressure backheat system include the low pressure jar, locate No. 1 low pressure heater, No. 2 low pressure heater, No. 3 low pressure heater, No. 4 low pressure heater on the heat transfer pipeline, the high pressure backheat system include the high pressure jar, locate No. 6 high pressure heater, No. 7 high pressure heater on the heat transfer pipeline, its characterized in that: the two-loop thermodynamic system further comprises a heating system, wherein the heating system comprises a heat generating device and a heat collecting and exchanging device which heats the condensed water in the heat exchanging pipeline by using the heat generated by the heat generating device.
2. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heat generating device is a solar photo-thermal device.
3. The nuclear power plant two-circuit thermodynamic system of claim 2, wherein: the solar photo-thermal device comprises a linear Fresnel reflection light-gathering system.
4. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heating system further comprises a heating pipeline, two end parts of the heating pipeline are respectively communicated with the heat exchange pipeline, and the heat collection and exchange device is arranged on the heating pipeline.
5. The nuclear power plant two-circuit thermodynamic system of claim 4, wherein: the heating system further comprises a bypass pipeline, two end parts of the bypass pipeline are respectively communicated with the heat exchange pipeline, and the bypass pipeline is connected with the heating pipeline in parallel.
6. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heat collection and exchange device is arranged at the downstream of any one of the No. 1 low-pressure heater, the No. 2 low-pressure heater, the No. 3 low-pressure heater, the No. 4 low-pressure heater, the No. 6 high-pressure heater and the No. 7 high-pressure heater.
7. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heat collection and exchange device is arranged at the downstream of the No. 4 low-pressure heater.
8. The nuclear power plant two-circuit thermodynamic system of claim 1, wherein: the heat collection and exchange device is arranged at the downstream of the No. 7 high-pressure heater.
9. The nuclear power plant two-circuit thermodynamic system of claim 5, wherein: the bypass pipeline is provided with a first switching valve; and two second switching valves are arranged on the heating pipeline and are respectively positioned at the upstream and the downstream of the heat collection and exchange device.
10. Use of a nuclear power plant two-circuit thermodynamic system as claimed in any one of claims 1 to 9, wherein: when the linear Fresnel reflection condensing system can receive solar radiation energy, the first switching valve is closed, and the second switching valve is opened, or the first switching valve and the second switching valve are both opened; when the linear Fresnel reflection condensation system cannot receive solar radiation energy, the first switching valve is opened, and the second switching valve is closed.
CN202011469157.0A 2020-12-15 2020-12-15 Nuclear power station two-loop thermodynamic system and using method thereof Pending CN112484011A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202011469157.0A CN112484011A (en) 2020-12-15 2020-12-15 Nuclear power station two-loop thermodynamic system and using method thereof

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202011469157.0A CN112484011A (en) 2020-12-15 2020-12-15 Nuclear power station two-loop thermodynamic system and using method thereof

Publications (1)

Publication Number Publication Date
CN112484011A true CN112484011A (en) 2021-03-12

Family

ID=74916373

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202011469157.0A Pending CN112484011A (en) 2020-12-15 2020-12-15 Nuclear power station two-loop thermodynamic system and using method thereof

Country Status (1)

Country Link
CN (1) CN112484011A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114001347A (en) * 2021-10-28 2022-02-01 华能山东石岛湾核电有限公司 High-temperature gas cooled reactor main feed water heating system and heating method

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114001347A (en) * 2021-10-28 2022-02-01 华能山东石岛湾核电有限公司 High-temperature gas cooled reactor main feed water heating system and heating method

Similar Documents

Publication Publication Date Title
CN101968041A (en) Solar power generation method and system taking biomass boiler as auxiliary heat source
CN108561282B (en) Trough type direct steam and molten salt combined thermal power generation system
CN108518324B (en) Tower type solar thermal coupling coal-fired power generation system with energy storage function
CN110863870B (en) Inclined temperature layer heat storage peak regulation system and peak regulation method based on high-pressure heating loop
CN204572366U (en) Enclosed Boulez is adopted to pause the tower-type solar thermal power generating system of circulation
CN111173697B (en) Solar tower trough combined power generation system
CN110761859B (en) Inclined temperature layer heat storage peak regulation system and peak regulation method based on low-pressure heating loop
CN109026240B (en) Power generation system and method based on nuclear energy and solar energy coupling
CN112484011A (en) Nuclear power station two-loop thermodynamic system and using method thereof
CN113834118A (en) Heating system based on Fresnel solar energy and combined cycle unit waste heat utilization
CN106762487B (en) Direct-expansion solar combined heat and power system with two-stage heat storage water tank
CN109139400B (en) Solar thermal complementary combined cycle system capable of changing integration mode based on irradiation change
CN214370112U (en) Nuclear power station two-loop thermodynamic system
US20130312413A1 (en) Steam rankine cycle solar plant and method for operating such plants
CN109519347B (en) Point-line focusing solar energy and coal-fired power station complementary power generation system and energy distribution method thereof
CN208204976U (en) A kind of low power focused solar energy heat-conserving energy-saving multi device
CN211950757U (en) Solar tower trough combined power generation system
CN114753898A (en) Reheating thermal power generating unit and photo-thermal combined power generation and steam supply system with peak regulation and energy storage functions
US20220145779A1 (en) Control method for optimizing solar-to-power efficiency of solar-aided coal-fired power system under off-design working conditions
CN114753897A (en) Reheating thermal power generating unit and photo-thermal combined power generation and steam supply system
CN113446175A (en) Point-line focusing combined solar thermal power generation system and method
CN204572364U (en) Enclosed Boulez pauses type tower-type solar thermal power generating system
CN208703575U (en) A kind of long range industry steam-supplying system for using vapour user for intermittence
CN208967879U (en) To the intermittent waste heat comprehensive utilization system with vapour user steam supply industrial over long distances
CN211953294U (en) System for tower light and heat spotlight solar collecting system provides heat transfer medium for SGS system

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination