CN111834026B - Industrial steam production system for pressurized water reactor nuclear power unit - Google Patents
Industrial steam production system for pressurized water reactor nuclear power unit Download PDFInfo
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- CN111834026B CN111834026B CN202010534718.4A CN202010534718A CN111834026B CN 111834026 B CN111834026 B CN 111834026B CN 202010534718 A CN202010534718 A CN 202010534718A CN 111834026 B CN111834026 B CN 111834026B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
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- 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
Abstract
The invention discloses an industrial steam production system for a pressurized water reactor nuclear power unit, which comprises: the nuclear steam supply device is a pressurized water reactor nuclear power unit which supplies heat source steam to the industrial steam production device while generating electricity; the inlet of the industrial steam production device is connected with the outlet of the nuclear steam supply device, heat source steam exchanges heat with feed water introduced into the industrial steam production device, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters for being conveyed to a heat user. The invention is based on the pressurized water reactor nuclear power unit, uses the two-loop main steam of the pressurized water reactor nuclear power unit to produce the industrial steam through the industrial steam production device, and conveys the industrial steam to users through the steam pipe network, thereby realizing the application of supplying clean industrial steam to the outside of the nuclear power station, developing a new way for comprehensively utilizing nuclear energy, effectively solving the environmental pollution caused by traditional energy sources such as coal and the like, improving the energy structure, ensuring the steam demand for industrial development and improving the economic benefit of the nuclear power station.
Description
Technical Field
The invention belongs to the technical field of comprehensive utilization of nuclear energy, and particularly relates to an industrial steam production system for a pressurized water reactor nuclear power unit.
Background
At present, industrial steam supply in China mainly comprises thermal power plants and boiler rooms, available fuels mainly comprise coal, and dust, sulfides, nitrogen oxides and carbon dioxide which are coal-fired emissions are main reasons of air pollution, haze and greenhouse effect. With the increasing number of nuclear power units and the continuous development of nuclear energy application technology in China, the nuclear energy multipurpose application, particularly the nuclear energy heating technology is mature, a plurality of nuclear power units supply heat for regional residents in a cogeneration mode at home and abroad, however, no nuclear power unit supplies industrial steam to the outside in China at present.
Disclosure of Invention
The technical problem to be solved by the invention is to provide an industrial steam production system for a pressurized water reactor nuclear power unit aiming at the defects in the prior art, provide a reasonable and feasible design scheme, realize the application of clean industrial steam externally supplied by a nuclear power station and develop a new way for comprehensively utilizing nuclear energy.
The technical scheme adopted for solving the technical problem is to provide an industrial steam production system for a pressurized water reactor nuclear power unit, which comprises the following components:
the nuclear steam supply device comprises a pressurized water reactor nuclear power unit, and the pressurized water reactor nuclear power unit provides heat source steam for the industrial steam production device while generating electricity;
the inlet of the industrial steam production device is connected with the outlet of the nuclear steam supply device, heat source steam exchanges heat with feed water introduced into the industrial steam production device, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters for being conveyed to a heat user.
Preferably, the nuclear steam supply device further includes a standby heat source, and the industrial steam production device is further connected to the standby heat source, and the standby heat source is configured to continuously supply the standby heat source steam to the industrial steam production device when the nuclear reactor of the nuclear steam supply device is shut down.
Preferably, the outlet of the industrial steam production device is connected with the nuclear steam supply device, the heat source steam flows into the industrial steam production device from the nuclear steam supply device, becomes nuclear steam hydrophobic after heat exchange is completed, and flows back to the nuclear steam supply device.
Preferably, the pressurized water reactor nuclear power plant includes:
a nuclear reactor for heating coolant;
the steam generator is connected with the nuclear reactor, is used for producing nuclear steam by using a coolant heated by the nuclear reactor, and is also connected with an industrial steam production device, and heat source steam in the steam generator flows to the industrial steam production device;
the steam turbine is connected with the steam generator and used for converting the heat energy of part of the nuclear steam into the rotational kinetic energy of the steam turbine;
the generator is connected with the steam turbine and driven by the steam turbine to generate electricity;
and the condenser is connected with the steam turbine and is used for condensing the exhaust steam which does work in the steam turbine into water, the condenser is also connected with the steam generator, and the exhaust steam condensate flows back to the steam generator after being heated by the steam extraction of the steam turbine and boosted by the main water feeding pump.
Preferably, the industrial steam generating apparatus includes:
the preheater group is connected with the evaporator group, and the heat source steam and the drain water flowing out of the evaporator group flow into the preheater group to exchange heat with the feed water introduced into the preheater group, so that the temperature of the feed water introduced into the preheater group is increased;
and the evaporator group is connected with the nuclear steam supply device, and heat source steam flowing out of the nuclear steam supply device exchanges heat with feed water flowing out of the preheater group in the evaporator group, so that the temperature of the feed water flowing into the evaporator group is increased, and industrial steam is obtained.
Preferably, the industrial steam producing apparatus further comprises:
and the superheater is connected with an outlet of the evaporator group for outputting industrial steam, and is used for further heating the industrial steam output by the evaporator group to a preset superheating temperature for conveying to a heat user.
Preferably, the superheater includes: the system comprises a superheater cold chamber and a superheater hot chamber which exchange heat with each other, wherein an inlet of the superheater hot chamber is connected with a nuclear steam supply device, and an outlet of the superheater cold chamber is used for conveying industrial steam to a heat user;
the evaporator group includes:
the primary evaporator comprises a primary evaporator cold chamber and a primary evaporator hot chamber which exchange heat with each other, the inlet of the primary evaporator hot chamber is connected with the outlet of the superheater hot chamber, and the outlet of the primary evaporator cold chamber is connected with the inlet of the superheater cold chamber;
the secondary evaporator comprises a secondary evaporator cold chamber and a secondary evaporator hot chamber which exchange heat with each other, the inlet of the secondary evaporator hot chamber is connected with the outlet of the primary evaporator hot chamber, and the outlet of the secondary evaporator cold chamber is connected with the inlet of the superheater cold chamber;
the preheater group includes:
the primary preheater comprises a primary preheater cold chamber and a primary preheater hot chamber which exchange heat with each other, wherein the inlet of the primary preheater hot chamber is connected with the outlet of the secondary evaporator hot chamber, the outlet of the primary preheater cold chamber is connected with the inlet of the secondary evaporator cold chamber, and the outlet of the primary preheater cold chamber is also connected with the inlet of the primary evaporator cold chamber;
the secondary preheater comprises a secondary preheater cold chamber and a secondary preheater hot chamber which exchange heat mutually, the inlet of the secondary preheater hot chamber is connected with the outlet of the primary preheater hot chamber, the outlet of the secondary preheater cold chamber is connected with the inlet of the primary preheater cold chamber, and the inlet of the secondary preheater cold chamber is used for inputting water.
Preferably, the industrial steam generating apparatus further comprises:
and the outlet of the deaerator is connected with the inlet of the primary preheater cold chamber.
Preferably, the outlet of the cold chamber of the superheater is connected with a deaerator for feeding industrial steam into the deaerator, and the deaerator deaerates water by using the industrial steam.
Preferably, the industrial steam generating apparatus further comprises:
and the radiation monitoring instrument is connected with an outlet of the superheater for outputting the industrial steam and is used for monitoring the radiation of the industrial steam.
The invention is based on the pressurized water reactor nuclear power unit, uses the two-loop main steam of the pressurized water reactor nuclear power unit to produce the industrial steam through the industrial steam production device, and transmits the industrial steam to users through the steam pipe network, thereby providing a complete, reasonable and feasible design scheme, realizing the application of the nuclear power station to externally supply clean industrial steam, and developing a new way for comprehensively utilizing nuclear energy. The pressurized water reactor nuclear power generating set has the characteristics of stable operation and high heat production capacity, industrial steam is supplied to the outside through the industrial steam production system, the problem of environmental pollution caused by traditional energy sources such as coal and the like can be solved while clean and efficient electric energy and industrial steam are provided, the energy structure is improved, the industrial development steam requirement is guaranteed, and the economic benefit of the nuclear power station is improved.
Drawings
Fig. 1 is a schematic configuration diagram of an industrial steam production system in embodiment 2 of the present invention.
In the figure: 1-nuclear steam supply, 101-nuclear reactor, 102-steam generator, 103-main pump, 104-turbine, 105-condenser, 106-main feed water pump, 107-generator, 108-backup heat source; 2-industrial steam production device, 201-pressure lift pump, 202-secondary preheater, 203-deaerator, 204-water feed pump, 205-primary preheater, 206-secondary evaporator, 207-primary evaporator, 208-superheater, 209-radiation monitoring instrument, 210-regulating valve; 81-the inlet of the superheater heat chamber; 82-outlet of the superheater heat chamber; 83-inlet of superheater cold chamber; 84-outlet of superheater cold chamber; 71-inlet of the first stage evaporator hot chamber; 72-outlet of the primary evaporator hot chamber; 73-the inlet of the cold chamber of the primary evaporator; 74-outlet of the primary evaporator cold chamber; 61-inlet of the hot chamber of the secondary evaporator; 62-outlet of the hot chamber of the secondary evaporator; 63-inlet of cold chamber of secondary evaporator; 64-outlet of the cold chamber of the secondary evaporator; 51-inlet of the primary preheater hot chamber; 52-outlet of the primary preheater hot chamber; 53-inlet of the primary preheater cold chamber; 54-outlet of the cold chamber of the primary preheater; 21-inlet of the secondary preheater hot chamber; 22-outlet of the secondary preheater hot chamber; 23-inlet of the cold chamber of the secondary preheater; 24-outlet of the cold chamber of the secondary preheater; 11-a main pipe; 12-a first branch pipe; 13-second branch.
Detailed Description
In order to make the technical solutions of the present invention better understood, the present invention is further described in detail with reference to the accompanying drawings and the detailed description below.
Reference will now be made in detail to embodiments of the present patent, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar function throughout. The embodiments described below with reference to the drawings are illustrative only for the purpose of explaining the present patent and are not to be construed as limiting the present patent.
Example 1
The embodiment provides an industrial steam production system for a pressurized water reactor nuclear power unit, comprising:
the nuclear steam supply device comprises a pressurized water reactor nuclear power unit, and the pressurized water reactor nuclear power unit provides heat source steam for the industrial steam production device while generating electricity;
the inlet of the industrial steam production device is connected with the outlet of the nuclear steam supply device, heat source steam exchanges heat with feed water introduced into the industrial steam production device, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters for being conveyed to a heat user.
The embodiment is based on a pressurized water reactor nuclear power unit, and the two-loop main steam of the pressurized water reactor nuclear power unit is used for producing industrial steam through an industrial steam production device and is conveyed to users through a steam pipe network, so that a complete, reasonable and feasible design scheme is provided, the application of clean industrial steam supplied by a nuclear power station to the outside is realized, and a new way of comprehensive utilization of nuclear energy is developed. The pressurized water reactor nuclear power generating set has the characteristics of stable operation and high heat production capacity, industrial steam is supplied to the outside through the industrial steam production system in the embodiment, the problem of environmental pollution caused by traditional energy sources such as coal and the like can be solved while clean and efficient electric energy and industrial steam are provided, the energy structure is improved, the industrial development steam requirement is guaranteed, and the economic benefit of the nuclear power station is improved.
Example 2
As shown in fig. 1, the present embodiment provides an industrial steam production system for a pressurized water reactor nuclear power plant, including:
the nuclear steam supply device 1 comprises a pressurized water reactor nuclear power generator set, and the pressurized water reactor nuclear power generator set provides heat source steam for the industrial steam production device 2 while generating electricity;
an inlet of the industrial steam production device 2 is connected with an outlet of the nuclear steam supply device 1, heat source steam exchanges heat with feed water introduced into the industrial steam production device 2, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters for being conveyed to a heat consumer, so that a nuclear power unit supplies the industrial steam.
Preferably, the nuclear steam supply device 1 further includes a standby heat source 108, the industrial steam production device 2 is further connected to the standby heat source 108, and the standby heat source 108 is configured to continuously supply steam from the standby heat source 108 to the industrial steam production device 2 when the nuclear reactor 101 of the nuclear steam supply device 1 is shut down, thereby ensuring continuous supply of industrial steam.
Preferably, an outlet of the industrial steam production device 2 is connected with the nuclear steam supply device 1, and the heat source steam flows into the industrial steam production device 2 from the nuclear steam supply device 1, becomes nuclear steam hydrophobic after heat exchange is completed, and flows back to the nuclear steam supply device 1. The heat source steam circulates between the nuclear steam supply device 1 and the industrial steam production device 2.
Preferably, the pressurized water reactor nuclear power plant includes:
a nuclear reactor 101 for heating coolant;
a steam generator 102 connected to the nuclear reactor 101, the steam generator 102 being configured to generate nuclear steam using coolant heated by the nuclear reactor 101, the steam generator 102 being further connected to the industrial steam generating apparatus 2, and heat source steam in the steam generator 102 flowing to the industrial steam generating apparatus 2; the pressurized water reactor nuclear power unit further comprises a main pump 103, the main pump 103 is arranged on a pipeline between the nuclear reactor 101 and the steam generator 102, and the main pump 103 is used for providing power for closed circulation of coolant. The high-temperature coolant heated by the nuclear reactor 101 is sent into the steam generator 102 through a pipeline, flows out of the steam generator 102 after heat exchange, flows into the main pump 103 through a pipeline to increase kinetic energy, and flows back to the nuclear reactor 101 through a pipeline to form a closed circulation loop.
A steam turbine 104 connected to the steam generator 102, the steam turbine 104 being configured to convert thermal energy of a part of the nuclear steam into rotational kinetic energy of the steam turbine 104; and the other part of nuclear steam is sent into the industrial steam production device 2 through a pipeline to provide heat source steam for steam conversion.
The generator 107 is connected with the steam turbine 104, the generator 107 generates electricity under the driving of the steam turbine 104, kinetic energy is converted into electric energy, and nuclear steam is used as dead steam after acting in the steam turbine 104;
the condenser 105 is connected with the turbine 104, the condenser 105 is further connected with the steam generator 102, the condenser 105 is used for condensing the exhaust steam which does work in the turbine 104 into water, and the exhaust steam condensed water flows back to the steam generator 102 after being heated by the steam extracted by the turbine 104 and being boosted by the main feed water pump 106. The condenser 105 is also connected with the industrial steam production device 2 and is used for collecting nuclear steam subjected to heat exchange in the industrial steam production device 2 and draining the nuclear steam. The pressurized water reactor nuclear power generating set further comprises a main water feed pump 106, the main water feed pump 106 is arranged on a pipeline between the condenser 105 and the steam generator 102, and the main water feed pump 106 provides kinetic energy for the circulation of the nuclear steam working medium in the nuclear steam supply device 1 to form a closed circulation loop.
Preferably, the industrial steam generating apparatus 2 includes:
the preheater group is connected with the evaporator group, and the heat source steam and the drain water flowing out of the evaporator group flow into the preheater group to exchange heat with the feed water introduced into the preheater group, so that the temperature of the feed water introduced into the preheater group is increased;
and the evaporator group is connected with the nuclear steam supply device 1, and heat source steam flowing out of the nuclear steam supply device 1 and feed water flowing out of the preheater group exchange heat in the evaporator group, so that the temperature of the feed water flowing into the evaporator group is increased, and industrial steam is obtained.
Preferably, the industrial steam production apparatus 2 further includes:
and the superheater 208 is connected with an outlet of the evaporator group for outputting the industrial steam, and the superheater 208 is used for further heating the industrial steam output by the evaporator group to a preset superheating temperature for conveying to a heat user.
Preferably, the superheater 208 includes: a superheater cold chamber and a superheater hot chamber which exchange heat with each other, wherein an inlet 81 of the superheater hot chamber is connected with the nuclear steam supply device 1, and an outlet 84 of the superheater cold chamber is used for conveying industrial steam to a heat user;
the evaporator group includes:
the primary evaporator 207 comprises a primary evaporator cold chamber and a primary evaporator hot chamber which exchange heat with each other, the inlet 71 of the primary evaporator hot chamber is connected with the outlet 82 of the superheater hot chamber, and the outlet 74 of the primary evaporator cold chamber is connected with the inlet 83 of the superheater cold chamber; the primary evaporator 207 produces industrial steam for nuclear steam. The heat source steam flows from the superheater 208 into the primary evaporator 207.
The secondary evaporator 206 comprises a secondary evaporator cold chamber and a secondary evaporator hot chamber which exchange heat with each other, wherein an inlet 61 of the secondary evaporator hot chamber is connected with an outlet 72 of the primary evaporator hot chamber, and an outlet 64 of the secondary evaporator cold chamber is connected with an inlet 83 of the superheater cold chamber; the secondary evaporator 206 produces industrial steam for nuclear steam dewatering.
The preheater group includes:
the primary preheater 205 comprises a primary preheater cold chamber and a primary preheater hot chamber which exchange heat with each other, wherein the inlet 51 of the primary preheater hot chamber is connected with the outlet 62 of the secondary evaporator hot chamber, the outlet 54 of the primary preheater cold chamber is connected with the inlet 63 of the secondary evaporator cold chamber, and the outlet 54 of the primary preheater cold chamber is also connected with the inlet 73 of the primary evaporator cold chamber;
the secondary preheater 202 comprises a secondary preheater cold chamber and a secondary preheater hot chamber which exchange heat with each other, wherein an inlet 21 of the secondary preheater hot chamber is connected with an outlet 52 of the primary preheater hot chamber, an outlet 24 of the secondary preheater cold chamber is connected with an inlet 53 of the primary preheater cold chamber, and an inlet 23 of the secondary preheater cold chamber is used for inputting feed water.
The steam generator 102 is connected to the inlet 81 of the superheater heat chamber and the backup heat source 108 is connected to the inlet 81 of the superheater heat chamber. Specifically, an inlet 81 of the superheater heating chamber is connected with an output end of a main pipe 11, an input end of the main pipe 11 is respectively connected with a first branch pipe 12 and a second branch pipe 13, the first branch pipe 12 is connected with a steam generator 102, and the second branch pipe 13 is connected with a standby heat source 108. The industrial steam production apparatus 2 further includes: the regulating valve 210 is arranged on the main pipe 11, and the regulating valve 210 regulates the amount of heat source steam extracted from the nuclear steam supply device 1 according to required industrial steam parameters and flow requirements.
Specifically, the industrial steam production apparatus 2 further includes: the pressure lift pump 201 is also arranged on the pipeline connected with the inlet 23 of the cold chamber of the secondary preheater 201. The pressure lift pump 201 is used to deliver demineralized water to the industrial steam production plant 2, continuously providing the feed water required for the production of industrial steam.
Specifically, the condenser 105 in this embodiment is connected to the outlet 22 of the hot chamber of the secondary preheater. The nuclear steam after heat exchange in the industrial steam production device 2 flows into the condenser 105 from the outlet 22 of the hot chamber of the secondary preheater.
Preferably, the industrial steam production apparatus 2 further includes:
and the deaerator 203 is used for deaerating, the inlet of the deaerator 203 is connected with the outlet 24 of the secondary preheater cold chamber, and the outlet of the deaerator 203 is connected with the inlet 53 of the primary preheater cold chamber.
Preferably, the outlet 84 of the superheater cold chamber is connected with the deaerator 203, the industrial steam flows into the deaerator 203 from the outlet 84 of the superheater cold chamber, and the deaerator 203 deaerates the feedwater by using the industrial steam self-produced by the industrial steam production device 2. The deaerator 203 tank ensures the consumption of the feed water of the primary evaporator 207 and the secondary evaporator 206 for a certain period of time.
Specifically, the industrial steam production device 2 further includes: and a feed water pump 204 is arranged on a pipeline between the inlet 53 of the primary preheater cold chamber and the deaerator 203. The feed water pump 204 is used to deliver feed water to the primary preheater 205 to provide kinetic energy to the feed water.
Preferably, the industrial steam production apparatus 2 further includes:
and a radiation monitoring instrument 209 connected with an outlet of the superheater 208 for outputting the industrial steam, wherein the radiation monitoring instrument 209 is used for monitoring the radiation of the industrial steam. The radiation monitoring instrument 209 is arranged on a pipeline connected with an outlet of the superheater 208 for outputting industrial steam, the industrial steam flows out from the industrial steam outlet of the superheater 208, flows through the radiation monitoring instrument 209 firstly, and is conveyed to a user heat supply network after being monitored to be free of radioactivity, so that radioactive substances are prevented from being released to a user side.
The primary evaporator 207 heats a part of the feed water from the primary preheater 205 by using heat of the heat source steam to generate required industrial steam, and the heat source steam is condensed into hydrophobic water after passing through the primary evaporator 207 and flows into the secondary evaporator 206. The secondary evaporator 206 heats another part of the feed water from the primary preheater 205 by using the heat of the hydrophobic heat source steam to generate the required industrial steam, and the hydrophobic heat source steam is cooled and then sent to the primary preheater 205 through a pipeline. The industrial steam generated by the primary evaporator 207 and the secondary evaporator 206 is collected and sent to the superheater 208 through a pipeline.
The primary preheater 205 heats the feed water supplied from the feed water pump 204 by using the drain of the heat source steam to meet the requirements of the primary evaporator 207 and the secondary evaporator 206 on the feed water temperature; the heat source steam drain water is subjected to heat exchange through the primary preheater 205 and then continuously enters the secondary preheater 202, and the secondary preheater 202 preheats the feed water by using the drain water of the heat source steam again, so that the heat of the heat source steam is utilized step by step.
The primary evaporator 207 and the secondary evaporator 206 heat the feed water from the primary preheater 205 by using the heat source steam and the hydrophobic heat to generate the required saturated industrial steam; the primary evaporator 207 produces industrial steam for nuclear steam, the secondary evaporator 206 produces industrial steam for nuclear steam drainage, and the heat of high-parameter heat source steam is fully utilized, so that the drainage temperature of the heat source steam after passing through the primary preheater 205 and the secondary preheater 202 is effectively reduced, and the heat efficiency of the industrial steam production system is improved.
The industrial steam production system for the pressurized water reactor nuclear power plant in the embodiment meets the related requirements of nuclear power plant design safety regulations (HAF 102) for preventing the radionuclide from migrating from the nuclear power plant to the heating device.
The industrial steam production system for the pressurized water reactor nuclear power unit in the embodiment utilizes the nuclear power unit to generate power and simultaneously produce clean industrial steam, so that comprehensive utilization of nuclear energy is realized.
The industrial steam production system for the pressurized water reactor nuclear power unit has the beneficial effects that:
(1) The embodiment uses the two-loop main steam of the pressurized water reactor nuclear power unit to carry out the production and supply of industrial steam through the steam conversion equipment, adopts the steam conversion technology, and the primary loop with radioactivity from the pressurized water reactor nuclear power unit is conducted to the two loops, and is conducted to the three loops of industrial steam by the two loops again, has realized the dual isolation of return circuit to through the reasonable setting of radioactivity monitoring devices, the radionuclide of nuclear power plant has been prevented from migrating outside the nuclear power plant.
(2) The embodiment provides a design scheme for producing and supplying industrial steam for the pressurized water reactor nuclear power unit, and is an effective way for solving the problem of environmental pollution caused by traditional energy sources such as coal and gas, improving the energy structure of China and ensuring clean energy supply required by industrial development.
It will be understood that the above embodiments are merely exemplary embodiments adopted to illustrate the principles of the present invention, and the present invention is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (7)
1. An industrial steam production system for a pressurized water reactor nuclear power plant, comprising:
the nuclear steam supply device comprises a pressurized water reactor nuclear power unit, and the pressurized water reactor nuclear power unit provides heat source steam for the industrial steam production device while generating electricity;
the inlet of the industrial steam production device is connected with the outlet of the nuclear steam supply device, heat exchange is carried out between heat source steam and feed water introduced into the industrial steam production device, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters for conveying to a heat user;
the industrial steam production device comprises:
the preheater group is connected with the evaporator group, and the heat source steam flowing out of the evaporator group flows into the preheater group to exchange heat with the feed water introduced into the preheater group, so that the temperature of the feed water introduced into the preheater group is increased;
the evaporator group is connected with the nuclear steam supply device, and heat source steam flowing out of the nuclear steam supply device exchanges heat with feed water flowing out of the preheater group in the evaporator group, so that the temperature of the feed water flowing into the evaporator group is increased, and industrial steam is obtained;
the industrial steam production apparatus further comprises:
the superheater is connected with an outlet of the evaporator group for outputting industrial steam, and is used for further heating the industrial steam output by the evaporator group to a preset superheating temperature for conveying to a heat user;
the superheater includes: the system comprises a superheater cold chamber and a superheater hot chamber which exchange heat with each other, wherein an inlet of the superheater hot chamber is connected with a nuclear steam supply device, and an outlet of the superheater cold chamber is used for conveying industrial steam to a heat user;
the evaporator set includes:
the primary evaporator comprises a primary evaporator cold chamber and a primary evaporator hot chamber which exchange heat with each other, wherein the inlet of the primary evaporator hot chamber is connected with the outlet of the superheater hot chamber, and the outlet of the primary evaporator cold chamber is connected with the inlet of the superheater cold chamber;
the secondary evaporator comprises a secondary evaporator cold chamber and a secondary evaporator hot chamber which exchange heat with each other, the inlet of the secondary evaporator hot chamber is connected with the outlet of the primary evaporator hot chamber, and the outlet of the secondary evaporator cold chamber is connected with the inlet of the superheater cold chamber;
the preheater group includes:
the primary preheater comprises a primary preheater cold chamber and a primary preheater hot chamber which exchange heat with each other, wherein the inlet of the primary preheater hot chamber is connected with the outlet of the secondary evaporator hot chamber, the outlet of the primary preheater cold chamber is connected with the inlet of the secondary evaporator cold chamber, and the outlet of the primary preheater cold chamber is also connected with the inlet of the primary evaporator cold chamber;
the secondary preheater comprises a secondary preheater cold chamber and a secondary preheater hot chamber which exchange heat mutually, the inlet of the secondary preheater hot chamber is connected with the outlet of the primary preheater hot chamber, the outlet of the secondary preheater cold chamber is connected with the inlet of the primary preheater cold chamber, and the inlet of the secondary preheater cold chamber is used for inputting water.
2. The industrial steam production system for a pressurized water reactor nuclear power plant according to claim 1, characterized in that the nuclear steam supply device further comprises a backup heat source, the industrial steam production device being further connected to the backup heat source, the backup heat source being configured to continuously supply backup heat source steam to the industrial steam production device when the nuclear reactor of the nuclear steam supply device is shut down.
3. The industrial steam production system for the pressurized water reactor nuclear power plant as claimed in claim 1, wherein an outlet of the industrial steam production device is connected with the nuclear steam supply device, and the heat source steam flows into the industrial steam production device from the nuclear steam supply device, becomes hydrophobic after heat exchange is completed, and flows back to the nuclear steam supply device.
4. The industrial steam production system for a pressurized water reactor nuclear power plant according to claim 1, characterized in that the pressurized water reactor nuclear power plant comprises:
a nuclear reactor for heating coolant;
the steam generator is connected with the nuclear reactor and used for generating nuclear steam by using a coolant heated by the nuclear reactor, the steam generator is also connected with an industrial steam generating device, and heat source steam in the steam generator flows to the industrial steam generating device;
the steam turbine is connected with the steam generator and used for converting the heat energy of part of the nuclear steam into the rotational kinetic energy of the steam turbine;
the generator is connected with the steam turbine and driven by the steam turbine to generate electricity;
and the condenser is connected with the steam turbine and is used for condensing the exhaust steam which does work in the steam turbine into water, the condenser is also connected with the steam generator, and the exhaust steam condensate flows back to the steam generator after being heated by the steam extraction of the steam turbine and boosted by the main water feeding pump.
5. The industrial steam production system for a pressurized water reactor nuclear power plant according to claim 1, further comprising:
and the outlet of the deaerator is connected with the inlet of the primary preheater cold chamber.
6. The industrial steam production system for the pressurized water reactor nuclear power plant of claim 5, wherein the outlet of the cold chamber of the superheater is connected to a deaerator for feeding industrial steam into the deaerator, and the deaerator uses the industrial steam to deaerate the feedwater.
7. The industrial steam production system for a pressurized water reactor nuclear power plant according to claim 1, characterized in that the industrial steam production plant further comprises:
and the radiation monitoring instrument is connected with an outlet of the superheater for outputting the industrial steam and is used for monitoring the radiation of the industrial steam.
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| CN102797523A (en) * | 2012-08-16 | 2012-11-28 | 中国核电工程有限公司 | Bleeder steam and exhaust steam comprehensive utilization method for nuclear turbine |
| CN203431826U (en) * | 2013-08-29 | 2014-02-12 | 北京京诚科林环保科技有限公司 | Steam turbine water supply heat regenerative system capable of recovering waste heat steam |
| CN107355260A (en) * | 2016-05-09 | 2017-11-17 | 中核辽宁核电有限公司 | A kind of co-generation unit based on large commercial nuclear power generating sets |
| CN107420878A (en) * | 2017-03-28 | 2017-12-01 | 中国核电工程有限公司 | It is a kind of to carry out vapour, heat, the system of CCHP using nuclear energy |
| CN209054540U (en) * | 2018-10-22 | 2019-07-02 | 中广核工程有限公司 | Nuclear energy heap comprehensive utilization system for heat energy |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101669733B1 (en) * | 2014-12-24 | 2016-10-26 | 이창건 | Energy-saving desalination system and method using steam generated in reactor |
-
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- 2020-06-12 CN CN202010534718.4A patent/CN111834026B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102797523A (en) * | 2012-08-16 | 2012-11-28 | 中国核电工程有限公司 | Bleeder steam and exhaust steam comprehensive utilization method for nuclear turbine |
| CN203431826U (en) * | 2013-08-29 | 2014-02-12 | 北京京诚科林环保科技有限公司 | Steam turbine water supply heat regenerative system capable of recovering waste heat steam |
| CN107355260A (en) * | 2016-05-09 | 2017-11-17 | 中核辽宁核电有限公司 | A kind of co-generation unit based on large commercial nuclear power generating sets |
| CN107420878A (en) * | 2017-03-28 | 2017-12-01 | 中国核电工程有限公司 | It is a kind of to carry out vapour, heat, the system of CCHP using nuclear energy |
| CN209054540U (en) * | 2018-10-22 | 2019-07-02 | 中广核工程有限公司 | Nuclear energy heap comprehensive utilization system for heat energy |
Non-Patent Citations (1)
| Title |
|---|
| 核热电联产系统与配汽方案分析优化;李素芬，徐士鸣，崔峨;《大连理工大学学报》;19940530(第03期);全文 * |
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