CN117727474B - Passive residual heat removal system for liquid metal cooled reactor - Google Patents
Passive residual heat removal system for liquid metal cooled reactor Download PDFInfo
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- CN117727474B CN117727474B CN202311605247.1A CN202311605247A CN117727474B CN 117727474 B CN117727474 B CN 117727474B CN 202311605247 A CN202311605247 A CN 202311605247A CN 117727474 B CN117727474 B CN 117727474B
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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
- Y02E30/30—Nuclear fission reactors
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Abstract
本申请提供了一种液态金属冷却反应堆的非能动余热排出系统，该非能动余热排出系统包括独立热交换器、空冷器、中间回路和多个斯特林热电转换器。空冷器包括风门。斯特林热电转换器的热端插入空冷器内以与中间回路换热，斯特林热电转换器的绝热端位于空冷器的内壁面，斯特林热电转换器的冷端位于空冷器的内壁面的外侧。当发生事故导致断电后，风门自动开启，利用斯特林热电转换器的冷端和热端之间的温差发电以供应急设备应用。本申请通过在非能动余热排出系统中增设斯特林热电转换器，从而充分利用液态金属冷却反应堆中液态金属冷却剂温度较高的优势，使得斯特林热电转换器能够利用余热发电供应核电厂内应急设备使用，降低了核电系统的复杂性。
The present application provides a passive waste heat removal system for a liquid metal cooled reactor, which includes an independent heat exchanger, an air cooler, an intermediate loop and a plurality of Stirling thermoelectric converters. The air cooler includes a damper. The hot end of the Stirling thermoelectric converter is inserted into the air cooler to exchange heat with the intermediate loop, the insulated end of the Stirling thermoelectric converter is located on the inner wall of the air cooler, and the cold end of the Stirling thermoelectric converter is located on the outer side of the inner wall of the air cooler. When an accident causes a power outage, the damper automatically opens, and the temperature difference between the cold end and the hot end of the Stirling thermoelectric converter is used to generate electricity for emergency equipment. The present application fully utilizes the advantage of the higher temperature of the liquid metal coolant in the liquid metal cooled reactor by adding a Stirling thermoelectric converter to the passive waste heat removal system, so that the Stirling thermoelectric converter can use waste heat to generate electricity for emergency equipment in the nuclear power plant, thereby reducing the complexity of the nuclear power system.
Description
Technical Field
The application belongs to the technical field of liquid metal cooling reactors, and particularly relates to an passive waste heat discharging system of a liquid metal cooling reactor.
Background
With the gradual maturity of nuclear power system technology, the development of nuclear power systems represented by liquid metal cooling reactors such as sodium-cooled fast reactors is rapid, and great demands are put forward on the safety of the liquid metal cooling reactors, and a reliable and passive safe passive waste heat discharging system is a key component of the liquid metal cooling reactors.
At present, a part or all of an passive waste heat discharging system of the liquid metal cooling reactor adopts a design scheme of an intermediate loop coupling air cooler, the starting time of accident waste heat discharging of the liquid metal cooling reactor is controlled by an air door of the air cooler, and under the condition of outage accidents of a whole plant, a nuclear power plant needs an emergency diesel engine to supply power, and the system is complex.
Disclosure of Invention
In view of the above, the embodiments of the present application are directed to providing an passive residual heat removal system for a liquid metal cooling reactor, in which a stirling thermoelectric converter is added to the passive residual heat removal system, so that the advantage of higher temperature of a liquid metal coolant in the liquid metal cooling reactor is fully utilized, the stirling thermoelectric converter can utilize residual heat to generate power for emergency equipment in a nuclear power plant, and the complexity of the nuclear power system is reduced.
The application provides a passive waste heat discharging system of a liquid metal cooling reactor, which comprises an independent heat exchanger, an air cooler, an intermediate loop and a plurality of Stirling thermoelectric converters. The independent heat exchanger is configured to exchange heat with heat generated by the liquid metal cooled reactor. The air cooler includes a damper. The inlet end of the air cooler is connected with the outlet end of the independent heat exchanger. The intermediate circuit is connected between the outlet end of the air cooler and the inlet end of the independent heat exchanger. The hot end of the Stirling thermoelectric converter is inserted into the air cooler to exchange heat with the intermediate circuit, the heat-insulating end of the Stirling thermoelectric converter is positioned on the inner wall surface of the air cooler, and the cold end of the Stirling thermoelectric converter is positioned on the outer side of the inner wall surface of the air cooler. The operation of the Stirling thermoelectric converter is controlled by opening and closing a damper of the air cooler, and when power failure occurs due to accident, the damper is automatically opened, and the temperature difference between the cold end and the hot end of the Stirling thermoelectric converter is utilized to generate power for emergency equipment application.
In the scheme, the plurality of Stirling thermoelectric converters are additionally arranged in the passive waste heat discharging system of the liquid metal cooling reactor, when an accident occurs and power failure occurs, the air door is automatically opened, the cold end of the Stirling thermoelectric converter exchanges heat with air in a convection mode, the temperature is reduced, the hot end of the Stirling thermoelectric converter absorbs heat of the middle loop, the temperature difference between the cold end and the hot end of the Stirling thermoelectric converter is large, power generation is caused, the generated power is enough for supplying emergency equipment application, waste heat discharging and emergency power supply are realized, the complexity of a nuclear power system is reduced, and the reliability of the nuclear power system is improved.
In one embodiment of the application, the liquid metal cooled reactor is a pool sodium cooled fast reactor. The independent heat exchanger is configured to be located within the liquid metal cooled reactor. The working medium of the Stirling thermoelectric converter is sodium.
In one embodiment of the application, the minimum threshold of the operating temperature range of the Stirling thermoelectric converter is not less than the outlet temperature of the liquid metal cooled reactor.
In one embodiment of the application, the liquid metal cooled reactor is a pool type sodium cooled fast reactor and the operating temperature range of the Stirling thermoelectric converter is 550 ℃ or higher.
Drawings
Fig. 1 is a schematic structural diagram of a passive residual heat removal system of a liquid metal cooling reactor according to an embodiment of the present application.
Detailed Description
The following description of the embodiments of the present application will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present application, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the application without making any inventive effort, are intended to be within the scope of the application.
As shown in fig. 1, the passive residual heat removal system 100 of the liquid metal cooled reactor 10 includes an independent heat exchanger 1, an air cooler 2, an intermediate circuit 3, and a plurality of stirling thermoelectric converters 4. The independent heat exchanger 1 is configured to exchange heat with heat generated by the liquid metal cooled reactor. The air cooler 2 includes a damper 21. The inlet end of the air cooler 2 is connected with the outlet end of the independent heat exchanger 1. The intermediate circuit 3 is connected between the outlet end of the air cooler 2 and the inlet end of the independent heat exchanger 1. The hot end a of the stirling thermoelectric converter 4 is inserted into the air cooler 2 to exchange heat with the intermediate circuit 3, the adiabatic end B of the stirling thermoelectric converter 4 is located on the inner wall surface of the air cooler 2, and the cold end C of the stirling thermoelectric converter 4 is located outside the inner wall surface S of the air cooler 2. The operation of the Stirling thermoelectric converter 4 is controlled by opening and closing the air door 21 of the air cooler 2, and when power failure occurs due to accident, the air door 21 is automatically opened, and power is generated by utilizing the temperature difference between the cold end C and the hot end A of the Stirling thermoelectric converter 4 to supply emergency equipment. In this way, by adding the plurality of stirling thermoelectric converters 4 in the passive residual heat removal system 100 of the liquid metal cooling reactor, when an accident occurs and power is cut off, the damper 21 is automatically opened, the cold end C of the stirling thermoelectric converter 4 exchanges heat with air in a convection manner, the temperature is reduced, the hot end a of the stirling thermoelectric converter 4 absorbs the heat of the intermediate circuit 3, and the temperature difference between the cold end C and the hot end a of the stirling thermoelectric converter 4 is large, so that power generation is caused, and the generated power is enough for emergency equipment application. In addition, the cold end C of the Stirling thermoelectric converter 4 arranged on the air cooler 2 and the independent heat exchanger 1 drive the intermediate circuit 3 to generate natural circulation, so that the waste heat discharge and emergency power supply can be simultaneously carried out, the complexity of a nuclear power system is reduced, the reliability of the nuclear power system is improved, and the Stirling thermoelectric converter has wide application prospect in a fast reactor passive waste heat discharge system adopting the intermediate circuit 3 to couple the air cooler 2.
When the liquid metal cooling reactor 10 is operating normally, the damper 21 of the air cooler 2 is closed, the air cooler 2 is not started, the temperature difference between the cold end C and the hot end a of the stirling thermoelectric converter 4 is small, and no heat is absorbed to generate electricity. In addition, after the accident occurs, the air door 21 can be automatically opened, and the Stirling thermoelectric converter is automatically put into use to provide the external power, so as to generate electricity and discharge heat.
The stirling thermoelectric converter 4 is a device for converting thermal energy into electric energy using the thermoelectric effect, and the operating principle of the stirling thermoelectric converter 4 is based on the thermodynamic principle of the stirling cycle, i.e., the generation of thermal energy by the temperature difference between two heat sources of different temperatures. The larger the temperature difference between the cold side C and the hot side a of the stirling thermoelectric converter 4, the higher the power generation efficiency.
In the passive residual heat removal system 100 of the liquid metal cooled reactor provided in at least one embodiment of the present application, the liquid metal cooled reactor 10 is a pool type sodium cooled fast reactor. The independent heat exchanger 1 is configured to be located within a liquid metal cooled reactor 10. The working medium of the Stirling thermoelectric converter 4 is sodium. In this way, the passive waste heat discharging system 100 is applied to the field of pool type sodium-cooled fast reactors, when an accident (such as a whole plant outage accident) occurs in a large pool type sodium-cooled fast reactor, the air door 21 is automatically opened after the power failure, the Stirling thermoelectric converter 4 generates heat in a loop to provide an emergency power supply, the temperature in the air cooler 2 is reduced, a natural circulation loop is formed by the passive waste heat discharging system and high-temperature fluid in the independent heat exchanger 1 in the pool type sodium-cooled fast reactor, and the passive waste heat discharging system continuously brings heat to the air cooler 2 to discharge the waste heat under the accident, and the passive waste heat discharging system 100 can be used for emergency equipment in a power plant by utilizing the waste heat to generate power.
The working temperature range of the stirling thermoelectric converter 4 is adapted to the outlet temperature of the reactor, and on this basis, the working temperature range of the stirling thermoelectric converter 4 is not particularly limited in the embodiment of the present application. In some embodiments, if the liquid metal cooled reactor is a pool-type sodium cooled fast reactor with an outlet temperature of about 550 ℃, the operating temperature range of the stirling thermoelectric converter 4 is above 550 ℃. In other embodiments, if the liquid metal cooled reactor is a lead alloy liquid metal cooled reactor having an outlet temperature of about 550 ℃, the operating temperature range of the stirling thermoelectric converter 4 is above 550 ℃.
It should be noted that, the combination of the technical features in the embodiment of the present application is not limited to the combination described in the embodiment of the present application or the combination described in the specific embodiment, and all the technical features described in the present application may be freely combined or combined in any manner unless contradiction occurs between them.
The foregoing description of the preferred embodiments of the application is not intended to be limiting, but rather is to be construed as including any modifications, equivalents, and alternatives falling within the spirit and principles of the application.
Claims (4)
1. A passive residual heat removal system for a liquid metal cooled reactor, comprising:
A separate heat exchanger configured to exchange heat generated by the liquid metal cooled reactor;
The air cooler comprises an air door, wherein the inlet end of the air cooler is connected with the outlet end of the independent heat exchanger;
an intermediate circuit connected between the outlet end of the air cooler and the inlet end of the independent heat exchanger;
the heat ends of the Stirling thermoelectric converters are inserted into the air cooler to exchange heat with the intermediate circuit, the heat insulation ends are positioned on the inner wall surface of the air cooler, the cold ends are positioned on the outer side of the inner wall surface of the air cooler, the operation of the Stirling thermoelectric converters is controlled by opening and closing a damper of the air cooler, after power failure is caused by accident, the damper is automatically opened, the cold ends of the Stirling thermoelectric converters exchange heat with air in a convection mode, and the hot ends of the Stirling thermoelectric converters absorb heat of the intermediate circuit and generate electricity by utilizing the temperature difference between the cold ends and the hot ends of the Stirling thermoelectric converters so as to supply emergency equipment application.
2. The passive waste heat removal system of claim 1, wherein,
The liquid metal cooling reactor is a pool type sodium-cooled fast reactor, the independent heat exchanger is configured to be positioned in the liquid metal cooling reactor, and the working medium of the Stirling thermoelectric converter is sodium.
3. The passive waste heat removal system of claim 1, wherein,
The minimum threshold of the operating temperature range of the Stirling thermoelectric converter is not less than the outlet temperature of the liquid metal cooled reactor.
4. The passive waste heat removal system of claim 3, wherein,
The liquid metal cooling reactor is a pool type sodium-cooled fast reactor, and the working temperature range of the Stirling thermoelectric converter is 550 ℃ or more.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN202311605247.1A CN117727474B (en) | 2023-11-27 | 2023-11-27 | Passive residual heat removal system for liquid metal cooled reactor |
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| CN202311605247.1A CN117727474B (en) | 2023-11-27 | 2023-11-27 | Passive residual heat removal system for liquid metal cooled reactor |
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| CN117727474A CN117727474A (en) | 2024-03-19 |
| CN117727474B true CN117727474B (en) | 2025-07-08 |
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| CN117476258A (en) * | 2023-11-27 | 2024-01-30 | 中核霞浦核电有限公司 | Accident passive waste heat removal system for liquid metal cooled reactor |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110310748A (en) * | 2019-07-02 | 2019-10-08 | 北京卫星环境工程研究所 | Integrated thermoelectric conversion reactor with turbine |
| CN110517796A (en) * | 2019-07-08 | 2019-11-29 | 华北电力大学 | A kind of improved passive residual heat removal system |
| CN114242278A (en) * | 2021-12-09 | 2022-03-25 | 中国船舶重工集团公司第七一九研究所 | A reactor waste heat removal system |
| CN117476258A (en) * | 2023-11-27 | 2024-01-30 | 中核霞浦核电有限公司 | Accident passive waste heat removal system for liquid metal cooled reactor |
Family Cites Families (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03279899A (en) * | 1990-03-29 | 1991-12-11 | Mitsubishi Heavy Ind Ltd | Fast breeder |
| WO1999044405A1 (en) * | 1998-02-27 | 1999-09-02 | Hi-Z Technology, Inc. | Thermoelectric generator for natural gas well head |
| AU4197999A (en) * | 1998-05-22 | 1999-12-13 | Bergstrom, Inc. | Auxiliary heating and air conditioning system for a motor vehicle |
| NO20110388A1 (en) * | 2011-03-14 | 2012-09-17 | Heggen Lars Harald | Method for operating coolant pumps and other equipment for nuclear power reactors by utilizing the energy in the reactor's coolant for operating Hot Gas Engines / Sterling Engines. |
| US9536629B2 (en) * | 2012-07-24 | 2017-01-03 | Westinghouse Electric Company Llc | Passive power production during a nuclear station blackout |
| RU2682722C1 (en) * | 2017-12-20 | 2019-03-21 | Федеральное государственное автономное образовательное учреждение высшего образования "Уральский федеральный университет имени первого Президента России Б.Н. Ельцина" | Npp reactor core energy releases controlled emergency removal system |
| CN111403059A (en) * | 2020-03-23 | 2020-07-10 | 西安交通大学 | Multipurpose dual-mode nuclear reactor power supply |
| CN113140334B (en) * | 2021-03-19 | 2022-02-18 | 中国核电工程有限公司 | Final heat trap system for active and passive cooperative cooling of nuclear power station |
| CN113669174B (en) * | 2021-08-16 | 2022-04-12 | 西安交通大学 | Multipurpose heat pipe pile prototype model machine |
| CN116659111A (en) * | 2023-05-31 | 2023-08-29 | 兰州空间技术物理研究所 | Stirling power supply device for space |
-
2023
- 2023-11-27 CN CN202311605247.1A patent/CN117727474B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110310748A (en) * | 2019-07-02 | 2019-10-08 | 北京卫星环境工程研究所 | Integrated thermoelectric conversion reactor with turbine |
| CN110517796A (en) * | 2019-07-08 | 2019-11-29 | 华北电力大学 | A kind of improved passive residual heat removal system |
| CN114242278A (en) * | 2021-12-09 | 2022-03-25 | 中国船舶重工集团公司第七一九研究所 | A reactor waste heat removal system |
| CN117476258A (en) * | 2023-11-27 | 2024-01-30 | 中核霞浦核电有限公司 | Accident passive waste heat removal system for liquid metal cooled reactor |
Non-Patent Citations (1)
| Title |
|---|
| 美新型同位素电力系统研发取得重要进展;伍浩松;张焰;国外核新闻;20231231(005);全文 * |
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