CN110148480A - A nuclear power secondary loop system - Google Patents
A nuclear power secondary loop system Download PDFInfo
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- CN110148480A CN110148480A CN201910451886.4A CN201910451886A CN110148480A CN 110148480 A CN110148480 A CN 110148480A CN 201910451886 A CN201910451886 A CN 201910451886A CN 110148480 A CN110148480 A CN 110148480A
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- G—PHYSICS
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- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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Abstract
本发明提供了一种核电二回路系统，包括蒸汽发生器系统、主蒸汽系统、和主给水系统，蒸汽发生器系统包括蒸汽发生器、主蒸汽隔离阀和主给水隔离阀，蒸汽发生器位于安全壳内，主蒸汽隔离阀、主蒸汽系统、主给水隔离阀和主给水系统位于安全壳外，蒸汽发生器与主蒸汽隔离阀间设有第一管道，主蒸汽隔离阀与主蒸汽系统间设有第二管道，蒸汽发生器与主给水隔离阀间设有第三管道，主给水隔离阀与主给水系统间设有第四管道，第一管道和第三管道与一回路反应堆冷却剂系统具有相同的设计压力。该核电二回路系统中，当蒸汽发生器的传热管出现断裂事故时，能避免向环境泄露放射性物质，还能防止质能释放导致的反应堆厂房超压。
The present invention provides a nuclear power secondary circuit system, including a steam generator system, a main steam system, and a main feedwater system. The steam generator system includes a steam generator, a main steam isolation valve, and a main feedwater isolation valve. The steam generator is located in a safe Inside the containment, the main steam isolation valve, main steam system, main feedwater isolation valve and main feedwater system are located outside the containment, the first pipeline is installed between the steam generator and the main steam isolation valve, and the main steam isolation valve and the main steam system are installed. There is a second pipeline, a third pipeline is provided between the steam generator and the main feedwater isolation valve, a fourth pipeline is provided between the main feedwater isolation valve and the main feedwater system, the first pipeline and the third pipeline are connected with the primary loop reactor coolant system same design pressure. In the nuclear power secondary circuit system, when the heat transfer tube of the steam generator breaks, it can avoid the leakage of radioactive substances to the environment, and can also prevent the overpressure of the reactor building caused by the release of mass and energy.
Description
技术领域technical field
本发明涉及核电站的安全技术领域，更具体的涉及一种核电二回路全压系统。The invention relates to the safety technical field of nuclear power plants, and more specifically relates to a nuclear power secondary circuit full pressure system.
背景技术Background technique
传统压水堆二回路系统1如图1所示，二回路中主给水系统2的给水经过蒸汽发生器3二次侧产生蒸汽，蒸汽经蒸汽管道4最终输送至汽轮机5做工，给水管道6和蒸汽管道4上分别设置主蒸汽隔离阀7和主给水隔离阀8，主蒸汽隔离阀7前设置一组安全阀9，主蒸汽隔离阀7和主给水隔离阀8及其之间管道的设计压力低于一回路(反应堆冷却剂系统)的设计压力，倘若蒸汽发生器3传热管出现破裂的事故(SGTR)或给水管道6、蒸汽管道4破裂的事故，一回路放射性的冷却剂通过破裂的传热管泄露至蒸汽发生器二次侧，造成蒸汽发生器二次侧的压力升高，随后主蒸汽隔离阀7和主给水隔离阀8进行隔离，主蒸汽安全阀9打开，二回路被放射性物质污染的蒸汽经安全阀9排向大气，不可避免的造成放射性物质向环境的释放。The traditional pressurized water reactor secondary circuit system 1 is shown in Figure 1. The feed water of the main water supply system 2 in the secondary circuit passes through the secondary side of the steam generator 3 to generate steam, and the steam is finally transported to the steam turbine 5 for work through the steam pipeline 4, and the water supply pipeline 6 and The main steam isolation valve 7 and the main feed water isolation valve 8 are respectively installed on the steam pipeline 4, and a group of safety valves 9 are arranged in front of the main steam isolation valve 7, and the design pressure of the main steam isolation valve 7, the main feed water isolation valve 8 and the pipelines between them Lower than the design pressure of the primary circuit (reactor coolant system), if the heat transfer tube of the steam generator 3 ruptures (SGTR) or the water supply pipe 6 and steam pipe 4 rupture, the radioactive coolant of the primary circuit passes through the ruptured The heat transfer tube leaked to the secondary side of the steam generator, causing the pressure on the secondary side of the steam generator to rise, and then the main steam isolation valve 7 and the main feed water isolation valve 8 were isolated, the main steam safety valve 9 was opened, and the secondary circuit was radioactive The material-contaminated steam is discharged to the atmosphere through the safety valve 9, which inevitably causes the release of radioactive materials to the environment.
因此，有必要提供一种核电二回路系统以解决现有的问题。Therefore, it is necessary to provide a nuclear power secondary circuit system to solve the existing problems.
发明内容Contents of the invention
本发明的目的在于提供一种核电二回路系统，在蒸汽发生器传热管断裂事故下，能避免向环境泄露放射性物质。The purpose of the present invention is to provide a nuclear power secondary circuit system, which can avoid leakage of radioactive substances to the environment in the event of a steam generator heat transfer tube rupture accident.
为实现上述目的，本发明提供了一种核电二回路系统，包括蒸汽发生器系统、主蒸汽系统和主给水系统，所述蒸汽发生器系统包括蒸汽发生器、主蒸汽隔离阀、和主给水隔离阀，所述蒸汽发生器位于安全壳内，所述主蒸汽隔离阀、主蒸汽系统、主给水隔离阀和主给水系统位于安全壳外，所述蒸汽发生器与所述主蒸汽隔离阀之间设有第一管道，所述主蒸汽隔离阀与所述主蒸汽系统之间设有第二管道，所述蒸汽发生器与所述主给水隔离阀之间设有第三管道，所述主给水隔离阀与所述主给水系统之间设有第四管道，所述主给水系统的给水经所述蒸汽发生器处理后流向所述主蒸汽系统，所述第一管道和所述第三管道与一回路反应堆冷却剂系统具有相同的设计压力。To achieve the above object, the present invention provides a nuclear power secondary circuit system, comprising a steam generator system, a main steam system and a main feed water system, the steam generator system including a steam generator, a main steam isolation valve, and a main feed water isolation Valve, the steam generator is located inside the containment, the main steam isolation valve, main steam system, main feedwater isolation valve and main feedwater system are located outside the containment, the steam generator and the main steam isolation valve A first pipeline is provided, a second pipeline is provided between the main steam isolation valve and the main steam system, a third pipeline is provided between the steam generator and the main feedwater isolation valve, and the main feedwater A fourth pipeline is provided between the isolation valve and the main water supply system. The feedwater of the main water supply system flows to the main steam system after being treated by the steam generator. The first pipeline and the third pipeline are connected with the The primary reactor coolant system has the same design pressure.
与现有技术相比，本申请的核电二回路系统中，主给水系统的给水经第四管道和第三管道输送至蒸汽发生器二次侧产生蒸汽，蒸汽经第一管道和第二管道输送至主蒸汽系统的汽轮发电机做功。其中，第一管道和第三管道与一回路(反应堆冷却剂系统)具有相同的设计压力，即蒸汽发生器系统全压设计。当蒸汽发生器的传热管出现断裂事故(SGTR)时，一回路放射性冷却剂通过蒸汽发生器传热管的破口处泄露到蒸汽发生器二次侧，此时主给水隔离阀和主蒸汽隔离阀进行隔离，将放射性物质被包容在蒸汽发生器二次侧，蒸汽发生器二次侧压力最大能达到一回路的设计压力，由于第一管道和所述第三管道与一回路反应堆冷却剂系统具有相同的设计压力，蒸汽发生器二次侧不会存在超压情况，放射性物质不会释放到环境中。因此，避免向环境泄露放射性物质，减少了二回路除盐除氧水的浪费。当第一管道或第三管道破裂时，主给水隔离阀和主蒸汽隔离阀进行隔离，能防止质能释放导致的反应堆厂房超压。还由于主蒸汽隔离阀与蒸汽发生器之间不设置安全阀，可避免安全阀误启动造成的事故工况。Compared with the prior art, in the nuclear power secondary circuit system of this application, the feed water of the main water supply system is transported to the secondary side of the steam generator through the fourth pipeline and the third pipeline to generate steam, and the steam is transported through the first pipeline and the second pipeline To the steam turbine generator of the main steam system to do work. Wherein, the first pipeline and the third pipeline have the same design pressure as the primary circuit (reactor coolant system), that is, the full pressure design of the steam generator system. When the heat transfer tube of the steam generator breaks (SGTR), the radioactive coolant of the primary circuit leaks to the secondary side of the steam generator through the break of the heat transfer tube of the steam generator. At this time, the main feed water isolation valve and the main steam The isolation valve is used to isolate the radioactive material on the secondary side of the steam generator, and the pressure on the secondary side of the steam generator can reach the design pressure of the primary circuit at most, because the first pipe and the third pipe are connected with the reactor coolant of the primary circuit The system has the same design pressure, there is no overpressure on the secondary side of the steam generator, and no radioactive material is released into the environment. Therefore, the leakage of radioactive substances to the environment is avoided, and the waste of desalination and deoxygenation water in the secondary circuit is reduced. When the first pipeline or the third pipeline breaks, the main feedwater isolation valve and the main steam isolation valve are isolated, which can prevent the overpressure of the reactor building caused by the release of mass and energy. In addition, since there is no safety valve between the main steam isolation valve and the steam generator, accident conditions caused by false activation of the safety valve can be avoided.
较佳的，所述蒸汽发生器内设有传热管，所述传热管与一回路反应堆冷却剂系统具有相同的设计压力。Preferably, heat transfer pipes are arranged inside the steam generator, and the heat transfer pipes have the same design pressure as the primary loop reactor coolant system.
较佳的，所述主蒸汽隔离阀和所述主给水隔离阀与一回路反应堆冷却剂系统具有相同的设计压力。Preferably, the main steam isolation valve and the main feedwater isolation valve have the same design pressure as the primary loop reactor coolant system.
较佳的，核电二回路系统还包括设置在所述第三管道且位于安全壳内的主给水止回阀，阻止水的回流。Preferably, the nuclear power secondary circuit system further includes a main feedwater check valve arranged in the third pipeline and inside the containment vessel to prevent water from flowing back.
较佳的，本申请的核电二回路系统还包括设置在所述第一管道且位于安全壳外的第一余热导出系统及设置在所述主给水止回阀与所述蒸汽发生器之间的第二余热导出系统，所述第一余热导出系统和所述第二余热导出系统用于将一回路产生的余热排出。Preferably, the nuclear power secondary circuit system of the present application further includes a first waste heat export system arranged in the first pipeline and outside the containment, and arranged between the main feedwater check valve and the steam generator The second waste heat export system, the first waste heat export system and the second waste heat export system are used to discharge the waste heat generated by the primary circuit.
较佳的，所述蒸汽发生器为直流蒸汽发生器。Preferably, the steam generator is a once-through steam generator.
附图说明Description of drawings
图1为现有技术中核电二回路系统的结构示意图。Fig. 1 is a schematic structural diagram of a nuclear power secondary circuit system in the prior art.
图2为本发明核电二回路系统的结构示意图。Fig. 2 is a structural schematic diagram of the nuclear power secondary circuit system of the present invention.
具体实施方式Detailed ways
现在参考附图描述本发明的实施例，附图中类似的元件标号代表类似的元件。Embodiments of the present invention will now be described with reference to the drawings, in which like reference numerals represent like elements.
请参考图1，本申请的核电二回路系统100，包括蒸汽发生器系统(图未示)、主蒸汽系统30和主给水系统50，蒸汽发生器系统包括蒸汽发生器10、主蒸汽隔离阀20和主给水隔离阀40，蒸汽发生器10位于安全壳内K1，主蒸汽隔离阀20、主蒸汽系统30、主给水隔离阀40和主给水系统50位于安全壳外K2，蒸汽发生器10与主蒸汽隔离阀20之间设有第一管道61，主蒸汽隔离阀20与主蒸汽系统30之间设有第二管道62，蒸汽发生器10与主给水隔离阀40之间设有第三管道63，主给水隔离阀40与主给水系统50之间设有第四管道64，主给水系统50的给水经蒸汽发生器10处理后流向主蒸汽系统30，第一管道61和第三管道63与一回路反应堆冷却剂系统具有相同的设计压力。Please refer to FIG. 1 , the nuclear power secondary circuit system 100 of the present application includes a steam generator system (not shown), a main steam system 30 and a main feed water system 50, and the steam generator system includes a steam generator 10 and a main steam isolation valve 20 and the main feedwater isolation valve 40, the steam generator 10 is located inside the containment K1, the main steam isolation valve 20, the main steam system 30, the main feedwater isolation valve 40 and the main feedwater system 50 are located outside the containment K2, the steam generator 10 and the main A first pipeline 61 is provided between the steam isolation valve 20, a second pipeline 62 is provided between the main steam isolation valve 20 and the main steam system 30, and a third pipeline 63 is provided between the steam generator 10 and the main feedwater isolation valve 40 A fourth pipeline 64 is provided between the main feedwater isolation valve 40 and the main water supply system 50, the feedwater of the main water supply system 50 flows to the main steam system 30 after being treated by the steam generator 10, the first pipeline 61 and the third pipeline 63 are connected with a Loop reactor coolant systems have the same design pressure.
进一步，蒸汽发生器10内设有传热管，传热管与一回路反应堆冷却剂系统具有相同的设计压力。本实施中蒸汽发生器10为直流蒸汽发生器10。更进一步，主蒸汽隔离阀20和主给水隔离阀40与一回路反应堆冷却剂系统具有相同的设计压力。也就是说当蒸汽发生器10内的传热管破裂，一回路反应堆冷却剂系统放射性冷却剂通过蒸汽发生器10传热管的破口处泄露到蒸汽发生器10二次侧，同时主蒸汽隔离阀20和主给水隔离阀40被操作进行隔离，由于二回路系统与一回路具有相同的设计压力，蒸汽发生器10二次侧不会超压，放射性物质不会释放到环境中。此外，当第一管道61、第二管道62、第三管道63或第四管道64破裂时，通过主蒸汽隔离阀20和主给水隔离阀40的隔离，也能防止质能释放导致的反应堆厂房超压。Further, heat transfer tubes are arranged inside the steam generator 10, and the heat transfer tubes have the same design pressure as the primary loop reactor coolant system. In this implementation, the steam generator 10 is a direct-flow steam generator 10 . Furthermore, the main steam isolation valve 20 and the main feed water isolation valve 40 have the same design pressure as the primary loop reactor coolant system. That is to say, when the heat transfer tube in the steam generator 10 breaks, the radioactive coolant of the primary circuit reactor coolant system leaks to the secondary side of the steam generator 10 through the breach of the heat transfer tube of the steam generator 10, and the main steam is isolated The valve 20 and the main feedwater isolation valve 40 are operated for isolation. Since the secondary circuit system has the same design pressure as the primary circuit, the secondary side of the steam generator 10 will not be overpressured and radioactive substances will not be released into the environment. In addition, when the first pipeline 61, the second pipeline 62, the third pipeline 63 or the fourth pipeline 64 rupture, the isolation of the main steam isolation valve 20 and the main feedwater isolation valve 40 can also prevent the reactor building from being damaged due to the release of mass energy. Overpressure.
请继续参考图1，核电二回路系统100还包括设置在第三管道63且位于安全壳内K1的主给水止回阀70，阻止水的回流。Please continue to refer to FIG. 1 , the nuclear power secondary circuit system 100 also includes a main feedwater check valve 70 arranged in the third pipeline 63 and located in K1 of the containment vessel to prevent water from flowing back.
请继续参考图1，本申请的核电二回路系统100还包括设置在第一管道61且位于安全壳外K2的第一余热导出系统80及设置在主给水止回阀70与蒸汽发生器10之间的第二余热导出系统90，第一余热导出系统80和第二余热导出系统90用于将一回路产生的余热排出，即能带出一回路反应堆余热。Please continue to refer to FIG. 1 , the nuclear power secondary circuit system 100 of the present application also includes a first waste heat derivation system 80 arranged on the first pipeline 61 and located outside the containment K2, and arranged on the main feedwater check valve 70 and the steam generator 10 The second waste heat export system 90 , the first waste heat export system 80 and the second waste heat export system 90 are used to discharge the waste heat generated in the primary circuit, that is, to take out the reactor waste heat in the primary circuit.
与现有技术相比，本申请的核电二回路系统100中，主给水系统50的给水经第四管道64和第三管道63输送至蒸汽发生器10二次侧产生蒸汽，蒸汽经第一管道61和第二管道62输送至主蒸汽系统30的汽轮发电机做功。其中，第一管道61和第三管道63与一回路(反应堆冷却剂系统)具有相同的设计压力。当蒸汽发生器10的传热管出现断裂事故(SGTR)时，一回路放射性冷却剂通过蒸汽发生器10传热管的破口处泄露到蒸汽发生器10二次侧，此时主给水隔离阀40和主蒸汽隔离阀20进行隔离，将放射性物质被包容在蒸汽发生器10二次侧，蒸汽发生器10二次侧压力最大能达到一回路的设计压力，由于第一管道61和所述第三管道63与一回路具有相同的设计压力，蒸汽发生器10二次侧不会存在超压情况，放射性物质不会释放到环境中。因此，避免向环境泄露放射性物质，减少了二回路除盐除氧水的浪费。当第一管道61或第三管道63破裂时，主给水隔离阀40和主蒸汽隔离阀20进行隔离，能防止质能释放导致的反应堆厂房超压。还由于主蒸汽隔离阀20与蒸汽发生器10之间不设置安全阀，可避免安全阀误启动造成的事故工况。Compared with the prior art, in the nuclear power secondary circuit system 100 of the present application, the feed water of the main water supply system 50 is transported to the secondary side of the steam generator 10 through the fourth pipeline 64 and the third pipeline 63 to generate steam, and the steam passes through the first pipeline 61 and the second pipeline 62 are sent to the steam turbine generator of the main steam system 30 for work. Wherein, the first pipeline 61 and the third pipeline 63 have the same design pressure as the primary circuit (reactor coolant system). When the heat transfer tube of the steam generator 10 breaks (SGTR), the primary loop of radioactive coolant leaks to the secondary side of the steam generator 10 through the break of the heat transfer tube of the steam generator 10, and the main feedwater isolation valve 40 is isolated from the main steam isolation valve 20, and the radioactive material is contained in the secondary side of the steam generator 10. The maximum pressure of the secondary side of the steam generator 10 can reach the design pressure of the primary circuit. Because the first pipeline 61 and the second The third pipeline 63 has the same design pressure as the primary circuit, so there will be no overpressure on the secondary side of the steam generator 10, and radioactive substances will not be released into the environment. Therefore, the leakage of radioactive substances to the environment is avoided, and the waste of desalination and deoxygenation water in the secondary circuit is reduced. When the first pipeline 61 or the third pipeline 63 breaks, the main feedwater isolation valve 40 and the main steam isolation valve 20 are isolated, which can prevent the overpressure of the reactor building caused by the release of mass energy. Furthermore, since no safety valve is provided between the main steam isolation valve 20 and the steam generator 10, accidental conditions caused by false activation of the safety valve can be avoided.
应当指出，以上具体实施方式仅用于说明本发明而不用于限制本发明的范围，在阅读了本发明之后，本领域技术人员对本发明的各种等价形式的修改均落入本申请所附权利要求限定的范围。It should be pointed out that the above specific embodiments are only used to illustrate the present invention and not to limit the scope of the present invention. The scope defined by the claims.
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111540487A (en) * | 2020-04-30 | 2020-08-14 | 中国核动力研究设计院 | Cooling treatment method for reactor after steam generator heat transfer pipe failure accident |
| CN115083631A (en) * | 2022-06-02 | 2022-09-20 | 中广核研究院有限公司 | Emergent waste heat discharge system of small-size pressurized water reactor of double loop |
| CN115083630A (en) * | 2022-06-02 | 2022-09-20 | 中广核研究院有限公司 | Secondary side waste heat discharge system of small pressurized water reactor |
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| CN115083631A (en) * | 2022-06-02 | 2022-09-20 | 中广核研究院有限公司 | Emergent waste heat discharge system of small-size pressurized water reactor of double loop |
| CN115083630A (en) * | 2022-06-02 | 2022-09-20 | 中广核研究院有限公司 | Secondary side waste heat discharge system of small pressurized water reactor |
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