CN115512866B - Multi-parameter long-distance nuclear energy steam supply system - Google Patents
Multi-parameter long-distance nuclear energy steam supply system Download PDFInfo
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- CN115512866B CN115512866B CN202211273483.3A CN202211273483A CN115512866B CN 115512866 B CN115512866 B CN 115512866B CN 202211273483 A CN202211273483 A CN 202211273483A CN 115512866 B CN115512866 B CN 115512866B
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 43
- 229920006395 saturated elastomer Polymers 0.000 claims abstract description 20
- 238000010612 desalination reaction Methods 0.000 claims description 22
- 239000013505 freshwater Substances 0.000 claims description 10
- 239000013535 sea water Substances 0.000 claims description 10
- 238000003860 storage Methods 0.000 claims description 4
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract description 4
- 229910052799 carbon Inorganic materials 0.000 abstract description 4
- 230000000694 effects Effects 0.000 abstract description 4
- 238000005261 decarburization Methods 0.000 abstract description 3
- 238000005265 energy consumption Methods 0.000 abstract description 3
- 239000000243 solution Substances 0.000 description 11
- 239000000126 substance Substances 0.000 description 7
- 239000003638 chemical reducing agent Substances 0.000 description 5
- 238000010793 Steam injection (oil industry) Methods 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000004566 building material Substances 0.000 description 1
- 239000002131 composite material Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000002803 fossil fuel Substances 0.000 description 1
- 238000009776 industrial production Methods 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000004753 textile Substances 0.000 description 1
Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22G—SUPERHEATING OF STEAM
- F22G1/00—Steam superheating characterised by heating method
- F22G1/005—Steam superheating characterised by heating method the heat being supplied by steam
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/08—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam
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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
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- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
The application discloses a multi-parameter long-distance nuclear energy steam supply system, which comprises a pressurized water reactor, a high-temperature gas cooled reactor, a nuclear power unit and a user side; the steam outlet side of the pressurized water reactor is provided with a first steam heat exchange assembly and supplies heat to the first steam heat exchange assembly in a circulating mode, the steam outlet side of the high-temperature gas cooled reactor is provided with a second steam heat exchange assembly and supplies heat to the second steam heat exchange assembly in a circulating mode, medium-low pressure saturated steam generated by the first steam heat exchange assembly enters the second steam heat exchange assembly to exchange heat, and the water outlet side of the nuclear power unit is provided with a circulating water treatment assembly. According to the application, the steam supply system fully utilizes the characteristics of high steam parameters and small quantity of the high-temperature gas cooled reactor and low steam parameters and large quantity of the pressurized water reactor, adopts a combined steam supply mode of the high-temperature gas cooled reactor and the pressurized water reactor, can realize the multi-parameter long-distance industrial steam supply effect, provides an industrial steam decarburization solution for high-energy-consumption enterprises, and solves the limitation brought by carbon discharge pressure.
Description
Technical Field
The application relates to the technical field of industrial steam supply, in particular to a multi-parameter long-distance nuclear energy steam supply system.
Background
The steam is one of the indispensable production materials in numerous industrial production, is widely applied to industries such as chemical industry, food, textile, building material manufacturing and the like, is especially used most widely in medium-pressure and low-pressure steam, has different steam supply schemes in different levels, and needs a large amount of steam with multiple parameters in a chemical industry park, the low-pressure steam demand is the largest, the high-pressure steam demand is relatively less, and in order to meet the steam demand of the chemical industry park, the multi-parameter steam supply of the steam is needed in the chemical industry park.
Chinese patent publication No.: CN113864747a discloses an industrial steam composite steam supply system, comprising: the system comprises a boiler, a high-pressure cylinder, a medium-pressure cylinder, a low-pressure cylinder, a condenser, a vapor compressor, a first temperature and pressure reducer, a vapor injection device and a second temperature and pressure reducer; the steam of the boiler enters a high-pressure cylinder to do work and then returns to the boiler to be heated again, reheat steam of the boiler is divided into four paths, the first path enters a second temperature and pressure reducer, the second path enters a high-pressure inlet of a steam injection device, the third path enters the first temperature and pressure reducer, and the fourth path enters a medium-pressure cylinder to do work; the steam at the outlet of the medium pressure cylinder is divided into two paths, one path enters the steam compressor, and the other path enters the low pressure cylinder; the exhaust steam of the steam compressor is divided into two paths, one path of the exhaust steam is converged with the steam of the first temperature and pressure reducing device and enters a low-pressure steam supply pipeline together, and the other path of the exhaust steam enters a low-pressure inlet of the steam injection device; the outlet steam of the steam injection device and the steam of the second temperature and pressure reducer are converged and jointly enter a high-pressure steam supply pipeline; the exhaust steam of the low-pressure cylinder enters a condenser to generate condensed water, and the condensed water in the condenser enters a boiler after being heated by a high-low pressure heater group, so that thermodynamic cycle is realized.
At present, a steam supply mode of a chemical industry park mainly obtains steam through modes of cogeneration of a thermal power unit or a self-provided boiler of a chemical industry enterprise and the like, and a large amount of fossil fuel is consumed in the mode, and a large amount of carbon emission is generated at the same time; the nuclear pressurized water reactor steam supply mode is also developed successively, but the steam parameters are lower, the main steam is saturated steam, only the requirements of low-pressure steam and short external supply conveying distance can be met, and the multi-parameter long-distance steam supply effect cannot be realized.
Disclosure of Invention
The application aims to provide a multi-parameter long-distance nuclear energy steam supply system which is used by combining a high-temperature gas cooled reactor and a pressurized water reactor and meets the multi-parameter long-distance industrial steam demand of a chemical industry park.
In order to achieve the above object, the present application provides the following technical solutions: a multi-parameter long-distance nuclear energy steam supply system comprises a pressurized water reactor, a high-temperature gas cooled reactor, a nuclear power unit and a user side;
the steam outlet side of the pressurized water reactor is provided with a first steam heat exchange assembly, and supplies heat to the first steam heat exchange assembly in a circulating way to generate medium-low pressure saturated steam;
the steam outlet side of the high-temperature gas cooled reactor is provided with a second steam heat exchange assembly, and supplies heat to the second steam heat exchange assembly in a circulating way to generate medium-high pressure superheated steam and flow the superheated steam into a user side;
the medium-low pressure saturated steam generated by the first steam heat exchange assembly enters the second steam heat exchange assembly for heat exchange, and then generates medium-low pressure superheated steam which flows into the user side;
the water outlet side of the nuclear power unit is provided with a circulating water treatment assembly and supplies water to the first steam heat exchange assembly and the second steam heat exchange assembly.
As a further description of the above technical solution:
the first steam heat exchange assembly consists of a first steam generator and a first heat exchanger, the first steam generator and the pressurized water reactor realize heat circulation flow, and the first heat exchanger and the first steam generator realize steam circulation flow.
As a further description of the above technical solution:
the second steam heat exchange assembly consists of a second steam generator and a superheater, wherein the second steam generator and the high-temperature gas cooled reactor realize heat circulation flow, and the superheater, the second heat exchanger and the second steam generator realize steam circulation flow.
As a further description of the above technical solution:
and the medium-low pressure saturated steam generated by the first heat exchanger enters the superheater to generate medium-low pressure superheated steam, and flows into the user side.
As a further description of the above technical solution:
and the superheated steam generated by the second steam generator enters the second heat exchanger to exchange heat, so as to generate medium-high pressure superheated steam and flow the medium-high pressure superheated steam into the user side.
As a further description of the above technical solution:
the circulating water treatment assembly consists of a sea water desalination system and a desalination reservoir, wherein the sea water desalination system is used for receiving circulating water discharged by a nuclear power unit, and fresh water generated after desalination flows into the desalination reservoir for storage and supplies water to the first heat exchanger and the second heat exchanger.
As a further description of the above technical solution:
after the fresh water in the desalination reservoir exchanges heat through the first heat exchanger, medium-low pressure saturated steam is generated and flows into the superheater; and after the fresh water in the desalination reservoir exchanges heat through the second heat exchanger, medium-high pressure superheated steam is generated and flows into the user side.
As a further description of the above technical solution:
the parameters of the medium-low pressure saturated steam and the medium-low pressure superheated steam are below 5.0MPa, and the parameters of the medium-high pressure superheated steam are 5.0-10.0 MPa.
In the technical scheme, the multi-parameter long-distance nuclear energy steam supply system provided by the application has the following beneficial effects:
the steam supply system fully utilizes the characteristics of high steam parameters and small quantity of the high-temperature gas cooled reactor and low steam parameters and large quantity of the pressurized water reactor, adopts a combined steam supply mode of the high-temperature gas cooled reactor and the pressurized water reactor, can realize the multi-parameter long-distance industrial steam supply effect, provides an industrial steam decarburization solution for high-energy-consumption enterprises, and solves the limit caused by carbon discharge pressure.
Drawings
In order to more clearly illustrate the embodiments of the present application or the technical solutions in the prior art, the drawings required for the embodiments will be briefly described below, and it is apparent that the drawings in the following description are only some embodiments described in the present application, and other drawings may be obtained according to these drawings for a person having ordinary skill in the art.
Fig. 1 is a schematic structural diagram of a multi-parameter long-distance nuclear energy steam supply system according to an embodiment of the present application.
Detailed Description
In order to make the technical scheme of the present application better understood by those skilled in the art, the present application will be further described in detail with reference to the accompanying drawings.
As shown in FIG. 1, the multi-parameter long-distance nuclear energy steam supply system comprises a pressurized water reactor, a high-temperature gas cooled reactor, a nuclear power unit and a user side;
the steam outlet side of the pressurized water reactor is provided with a first steam heat exchange assembly, and supplies heat to the first steam heat exchange assembly in a circulating way to generate medium-low pressure saturated steam;
the steam outlet side of the high-temperature gas cooled reactor is provided with a second steam heat exchange assembly, and supplies heat to the second steam heat exchange assembly in a circulating way to generate medium-high pressure superheated steam and flow the superheated steam into a user side;
after the medium-low pressure saturated steam generated by the first steam heat exchange component enters the second steam heat exchange component for heat exchange, medium-low pressure superheated steam is generated and flows into the user side;
the water outlet side of the nuclear power unit is provided with a circulating water treatment assembly and supplies water to the first steam heat exchange assembly and the second steam heat exchange assembly.
The steam supply system fully utilizes the characteristics of high steam parameters and small quantity of the high-temperature gas cooled reactor and low steam parameters and large quantity of the pressurized water reactor, adopts a combined steam supply mode of the high-temperature gas cooled reactor and the pressurized water reactor, can realize the multi-parameter long-distance industrial steam supply effect, provides an industrial steam decarburization solution for high-energy-consumption enterprises, and solves the limit caused by carbon discharge pressure.
The first steam heat exchange assembly consists of a first steam generator and a first heat exchanger, the first steam generator and the pressurized water reactor realize heat circulation flow, and the first heat exchanger and the first steam generator realize steam circulation flow.
The second steam heat exchange assembly consists of a second steam generator and a superheater, wherein the second steam generator and the high-temperature gas cooled reactor realize heat circulation flow, and the superheater, the second heat exchanger and the second steam generator realize steam circulation flow.
The medium-low pressure saturated steam generated by the first heat exchanger enters the superheater to generate medium-low pressure superheated steam, and the medium-low pressure superheated steam flows into the user side.
The superheated steam generated by the second steam generator enters the second heat exchanger to exchange heat, and medium-high pressure superheated steam is generated and flows into the user side.
The circulating water treatment assembly consists of a sea water desalination system and a desalination reservoir, wherein the sea water desalination system is used for receiving circulating water discharged by the nuclear power unit, and fresh water generated after desalination flows into the desalination reservoir for storage and supplies water to the first heat exchanger and the second heat exchanger.
After the fresh water in the desalination reservoir exchanges heat through the first heat exchanger, medium-low pressure saturated steam is generated and flows into the superheater; and after the fresh water in the desalination reservoir exchanges heat through the second heat exchanger, medium-high pressure superheated steam is generated and flows into the user side.
The parameters of the medium-low pressure saturated steam and the medium-low pressure superheated steam are below 5.0MPa, and the parameters of the medium-high pressure superheated steam are 5.0-10.0 MPa.
The steam supply steps of the nuclear energy steam supply system are as follows:
s01: the circulating water drainage of the nuclear power unit is used as the water inlet of the sea water desalination, and after the sea water is desalinated by a sea water desalination system, the sea water enters a fresh water reservoir for storage and use;
s02: saturated steam with pressure of 5.0MPa and below generated by a first steam generator by utilizing heat of a pressurized water reactor, and medium-low pressure saturated steam with pressure of 5.0MPa and below generated by a first heat exchanger;
s03: after the main steam of the high-temperature gas cooled reactor is used for superheating the medium-low pressure saturated steam, medium-low pressure superheated steam with the pressure of 5MPa or below is generated and is supplied to a user side for use through the outside of a long-distance pipeline network;
s04: the heat of the high-temperature gas cooled reactor is utilized to generate 14.1MPa of superheated steam through a second steam generator, and then the superheated steam is generated into 5.0MPa-10MPa of medium-high pressure superheated steam through a second heat exchanger, and the superheated steam is supplied to a user side through a long-distance pipeline network.
While certain exemplary embodiments of the present application have been described above by way of illustration only, it will be apparent to those of ordinary skill in the art that modifications may be made to the described embodiments in various different ways without departing from the spirit and scope of the application. Accordingly, the drawings and description are to be regarded as illustrative in nature and not as restrictive of the scope of the application, which is defined by the appended claims.
Claims (5)
1. The multi-parameter long-distance nuclear energy steam supply system is characterized by comprising a pressurized water reactor, a high-temperature gas cooled reactor, a nuclear power unit and a user side;
the steam outlet side of the pressurized water reactor is provided with a first steam heat exchange assembly, and supplies heat to the first steam heat exchange assembly in a circulating way to generate medium-low pressure saturated steam;
the first steam heat exchange assembly consists of a first steam generator and a first heat exchanger, wherein the first steam generator and the pressurized water reactor realize heat circulation flow, and the first heat exchanger and the first steam generator realize steam circulation flow;
the steam outlet side of the high-temperature gas cooled reactor is provided with a second steam heat exchange assembly, and supplies heat to the second steam heat exchange assembly in a circulating way to generate medium-high pressure superheated steam and flow the superheated steam into a user side;
the second steam heat exchange assembly consists of a second steam generator, a superheater and a second heat exchanger, wherein the second steam generator and the high-temperature gas cooled reactor realize heat circulation flow, and the superheater and the second heat exchanger realize steam circulation flow;
the medium-low pressure saturated steam generated by the first steam heat exchange assembly enters the second steam heat exchange assembly for heat exchange, and then generates medium-low pressure superheated steam which flows into the user side;
the water outlet side of the nuclear power unit is provided with a circulating water treatment assembly and supplies water to the first steam heat exchange assembly and the second steam heat exchange assembly;
and the medium-low pressure saturated steam generated by the first heat exchanger enters the superheater to generate medium-low pressure superheated steam, and flows into the user side.
2. A multiparameter, long-range nuclear power steam supply system according to claim 1, wherein: and the superheated steam generated by the second steam generator enters the second heat exchanger to exchange heat, so as to generate medium-high pressure superheated steam and flow the medium-high pressure superheated steam into the user side.
3. A multiparameter, long-range nuclear power steam supply system according to claim 1, wherein: the circulating water treatment assembly consists of a sea water desalination system and a desalination reservoir, wherein the sea water desalination system is used for receiving circulating water discharged by a nuclear power unit, and the desalinated fresh water flows into the desalination reservoir for storage and is supplied to the first heat exchanger and the second heat exchanger.
4. A multiparameter, long-range nuclear power steam supply system according to claim 3, wherein: after the fresh water in the desalination reservoir exchanges heat through the first heat exchanger, medium-low pressure saturated steam is generated and flows into the superheater; and after the fresh water in the desalination reservoir exchanges heat through the second heat exchanger, medium-high pressure superheated steam is generated and flows into the user side.
5. A multiparameter, long-range nuclear power steam supply system according to claim 1, wherein: the parameters of the medium-low pressure saturated steam and the medium-low pressure superheated steam are below 5.0MPa, and the parameters of the medium-high pressure superheated steam are 5.0-10.0 MPa.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310901826.4A CN116857634A (en) | 2022-10-18 | 2022-10-18 | Steam supply method of heat supply pipe network |
| CN202211273483.3A CN115512866B (en) | 2022-10-18 | 2022-10-18 | Multi-parameter long-distance nuclear energy steam supply system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211273483.3A CN115512866B (en) | 2022-10-18 | 2022-10-18 | Multi-parameter long-distance nuclear energy steam supply system |
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| CN202310901826.4A Division CN116857634A (en) | 2022-10-18 | 2022-10-18 | Steam supply method of heat supply pipe network |
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| Publication Number | Publication Date |
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| CN115512866A CN115512866A (en) | 2022-12-23 |
| CN115512866B true CN115512866B (en) | 2023-08-11 |
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| CN202211273483.3A Active CN115512866B (en) | 2022-10-18 | 2022-10-18 | Multi-parameter long-distance nuclear energy steam supply system |
| CN202310901826.4A Pending CN116857634A (en) | 2022-10-18 | 2022-10-18 | Steam supply method of heat supply pipe network |
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2008077297A1 (en) * | 2006-12-22 | 2008-07-03 | China Nuclear Power Design Company Ltd. (Shenzhen) | Multi-reactors combine nuclear fuel cycle using method |
| CN101908386A (en) * | 2010-06-21 | 2010-12-08 | 华北电力大学 | Pressurized water reactor and high-temperature gas cooled reactor-based hybrid thermodynamic cycle system |
| 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 |
| CN113113161A (en) * | 2021-04-06 | 2021-07-13 | 上海核工程研究设计院有限公司 | Nuclear energy steam supply system |
-
2022
- 2022-10-18 CN CN202211273483.3A patent/CN115512866B/en active Active
- 2022-10-18 CN CN202310901826.4A patent/CN116857634A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2008077297A1 (en) * | 2006-12-22 | 2008-07-03 | China Nuclear Power Design Company Ltd. (Shenzhen) | Multi-reactors combine nuclear fuel cycle using method |
| CN101908386A (en) * | 2010-06-21 | 2010-12-08 | 华北电力大学 | Pressurized water reactor and high-temperature gas cooled reactor-based hybrid thermodynamic cycle system |
| 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 |
| CN113113161A (en) * | 2021-04-06 | 2021-07-13 | 上海核工程研究设计院有限公司 | Nuclear energy steam supply system |
Non-Patent Citations (1)
| Title |
|---|
| 王盟等.提高压水堆循环热效率的方案设计.应用科技.2010,第37卷(第8期),49-52. * |
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| CN116857634A (en) | 2023-10-10 |
| CN115512866A (en) | 2022-12-23 |
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