CN112053791B - Non-time-limit passive combined heat removal system with integrated heat release trap - Google Patents
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- G—PHYSICS
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- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
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- G—PHYSICS
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- G21C9/004—Pressure suppression
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Abstract
本发明提供一种具有集成释热阱的无时限非能动联合排热系统,在双层混凝的安全壳夹层气空间的中下部设置有集成释热阱,集成释热阱是由耐腐蚀金属板围成的环形水池,安全壳夹层上部气空间的内层安全壳壁面上设置有至少一组的通往安全壳内部气空间的联通管线和单向阀,所述集成释热阱连接有安全壳快速泄压系统、自动泄压系统、非能动余热排出系统、非能动低压安注系统、非能动堆腔注水系统、过滤排放系统,本发明用以简化核电厂反应堆系统布置、缩小安全壳体积、为安全壳提供无时限的热量导出,最终为提高先进核动力电厂的经济性和非能动安全性提供可行方案。
The invention provides a timeless passive combined heat removal system with an integrated heat release trap. An integrated heat release trap is provided in the middle and lower part of the interlayer gas space of the double-layer coagulated containment vessel. The integrated heat release trap is made of corrosion-resistant metal An annular water pool surrounded by plates, the inner containment wall of the upper air space of the containment interlayer is provided with at least one set of communication pipelines leading to the internal air space of the containment and a one-way valve, and the integrated heat release well is connected with a safety Shell rapid pressure relief system, automatic pressure relief system, passive waste heat discharge system, passive low pressure safety injection system, passive reactor cavity water injection system, filter discharge system, the invention is used to simplify the reactor system layout of nuclear power plants and reduce the containment volume , Provide timeless heat export for the containment, and finally provide a feasible solution for improving the economy and passive safety of advanced nuclear power plants.
Description
技术领域technical field
本发明涉及先进核动力电厂中的非能动安全系统,尤其涉及一种具有集成释热阱的无时限非能动联合排热系统。The invention relates to a passive safety system in an advanced nuclear power plant, in particular to a timeless passive combined heat removal system with an integrated heat sink.
背景技术Background technique
自上个世纪六七十年代核能实现大规模商用以来,其长期为人类提供着清洁高效的能源。由于核电厂运行过程中具有潜在的放射性风险,其安全性始终受到业界人士尤其是研发人员的高度关注。Since the large-scale commercial use of nuclear energy in the 1960s and 1970s, it has provided mankind with clean and efficient energy for a long time. Due to the potential radioactive risks in the operation of nuclear power plants, their safety has always been highly concerned by people in the industry, especially R&D personnel.
迄今为止,核能领域曾发生过三次较为严重的事故:一是美国三哩岛核事故,二是苏联切尔诺贝利核事故,三是日本福岛核事故。从三次核事故中总结得到的深刻教训在于人为操作失误很可能导致反应堆发生严重事故;能动安全设施在全厂断电事故条件下具有较大的安全隐患。如何采用非能动安全系统长期导出反应堆/安全壳内的余热以增强核电厂的固有安全性并为操纵员的干预提供充足的判断时间成为第三代核电机组研发的重点之一。So far, there have been three relatively serious accidents in the field of nuclear energy: the first is the Three Mile Island nuclear accident in the United States, the second is the Chernobyl nuclear accident in the Soviet Union, and the third is the Fukushima nuclear accident in Japan. The profound lessons learned from the three nuclear accidents are that human error is likely to lead to serious accidents in the reactor; active safety facilities have greater safety hazards under the conditions of power failure in the whole plant. How to use the passive safety system to remove the waste heat in the reactor/containment for a long time to enhance the inherent safety of the nuclear power plant and provide sufficient judgment time for the operator's intervention has become one of the focuses of the third-generation nuclear power unit research and development.
我国拥有完全自主产权的第三代核电机组“华龙一号”针对潜在的反应堆事故创新性的引入了能动与非能动相结合的设计理念。在非能动安全系统方面针对主冷却剂回路和二次侧设置有非能动安注系统、非能动余热排出系统、非能动堆腔注水系统。针对核电厂的最后一道安全屏障——双层混凝土安全壳设置有非能动安全壳热量导出系统。这些系统的协调运行可有效抵御核电厂全厂断电事故并为操纵员提供72小时的不干预时间。my country's third-generation nuclear power unit "Hualong One", which has completely independent property rights, innovatively introduced the design concept of combining active and passive for potential reactor accidents. In terms of passive safety systems, a passive safety injection system, a passive waste heat removal system, and a passive reactor cavity water injection system are provided for the main coolant circuit and the secondary side. The last safety barrier for nuclear power plants—the double-layer concrete containment vessel is equipped with a passive containment heat export system. The coordinated operation of these systems can effectively resist the blackout accident of the nuclear power plant and provide the operator with 72 hours of non-intervention time.
关于先进核能技术,已有的发明专利公开了一些非能动安全系统。其中,公开号为CN111128414A、CN111383782A的专利提供了若干非能动安全系统,包括非能动安全壳排热系统、二次侧非能动余热排出系统、非能动安注系统等,授权号为CN209149827U、公开号为CN110021447A的专利提供了非能动的二次侧余热排出系统,公开号为CN110400644A、CN106024077A的专利分别公开了一种非能动的安全壳热量排出系统。这些专利的特点在于主要关注各非能动系统的布置方案,在设计上并没有考虑不同非能动安全系统间的相互关系。典型的,不同的非能动安全系统中有各自的热阱,这导致安全壳内/外侧需要在不同的空间位置处布置多个冷却水箱/蓄水箱,这不利于核电厂复杂回路的简化与建造成本的降低。With regard to advanced nuclear technology, existing invention patents disclose some passive safety systems. Among them, patents with publication numbers CN111128414A and CN111383782A provide several passive safety systems, including passive containment heat removal system, secondary side passive waste heat removal system, passive safety injection system, etc., the authorization number is CN209149827U, publication number Patent CN110021447A provides a passive secondary side waste heat removal system, and patents with publication numbers CN110400644A and CN106024077A respectively disclose a passive containment heat removal system. The characteristic of these patents is that they mainly focus on the layout scheme of each passive system, and do not consider the mutual relationship between different passive safety systems in design. Typically, different passive safety systems have their own heat sinks, which leads to the need to arrange multiple cooling water tanks/water storage tanks at different spatial positions inside/outside the containment, which is not conducive to the simplification and integration of complex circuits in nuclear power plants. Reduced construction costs.
在安全壳热量导出方面,根据事故发展的进程,安全壳内部气空间将形成2个压力峰值,一是大破口喷放初期的几十秒内在安全壳内形成的幅值较高的第一个压力峰值,二是堆芯再淹没后进行长期冷却过程中所形成的第二个压力峰值。关于安全壳气空间压力缓解的方案,已公开的专利主要针对第二个压力峰值,在缓解安全壳第一个压力峰值方面并没有形成有效方案,主要通过尽可能增大安全壳体积以增强安全壳气空间的缓冲能力,这增加了核电厂安全壳的体积和建造成本。In terms of heat export from the containment, according to the progress of the accident, two pressure peaks will be formed in the gas space inside the containment, one is the first one with a higher amplitude formed in the containment within tens of seconds of the initial stage of large breach discharge. The pressure peak, the second is the second pressure peak formed during the long-term cooling process of the core after reflooding. With regard to the solution for pressure relief in the gas space of the containment, the published patents are mainly aimed at the second peak pressure, and there is no effective solution for relieving the first peak pressure of the containment, mainly by increasing the volume of the containment as much as possible to enhance safety. The buffer capacity of the shell gas space, which increases the volume and construction cost of the nuclear power plant containment.
可以看出已有非能动安全系统的进一步发展主要限制于以下三点:一是如何在较小的安全壳容积下有效应对大破口事故的第一个压力峰值;二是如何通过有效的集成不同非能动系统的释热阱,以简化系统布置,降低设备冗余度;三是如何完成安全壳的无时限热量导出。It can be seen that the further development of existing passive safety systems is mainly limited by the following three points: first, how to effectively deal with the first pressure peak of a large breach accident with a small containment volume; second, how to effectively integrate different The heat release sink of the passive system to simplify the system layout and reduce equipment redundancy; the third is how to complete the unlimited time-limited heat export of the containment.
因此,有必要发明一种具有集成释热阱的无时限非能动联合排热系统,以简化反应堆系统布置、缩小安全壳体积、为安全壳提供无时限的热量导出,最终为先进核动力电厂的经济性和非能动安全性提供可行方案。Therefore, it is necessary to invent a timeless passive combined heat removal system with an integrated heat release sink to simplify the layout of the reactor system, reduce the volume of the containment vessel, provide timeless heat export for the containment vessel, and ultimately provide a basis for the development of advanced nuclear power plants. Economical and passive safety provide a feasible solution.
发明内容Contents of the invention
本发明的目的是为了提供一种具有集成释热阱的无时限非能动联合排热系统,用以简化核电厂反应堆系统布置、缩小安全壳体积、为安全壳提供无时限的热量导出,最终为提高先进核动力电厂的经济性和非能动安全性提供可行方案。The purpose of the present invention is to provide a timeless passive combined heat removal system with an integrated heat sink, which is used to simplify the layout of the nuclear power plant reactor system, reduce the volume of the containment vessel, provide timeless heat export for the containment vessel, and ultimately provide It provides a feasible solution to improve the economics and passive safety of advanced nuclear power plants.
本发明的目的是这样实现的:在双层混凝的安全壳夹层气空间的中下部设置有集成释热阱,集成释热阱是由耐腐蚀金属板围成的环形水池,安全壳夹层上部气空间的内层安全壳壁面上设置有至少一组的通往安全壳内部气空间的联通管线和单向阀,所述集成释热阱连接有安全壳快速泄压系统、自动泄压系统、非能动余热排出系统、非能动低压安注系统、非能动堆腔注水系统、过滤排放系统,安全壳快速泄压系统、自动泄压系统、非能动余热排出系统、非能动低压安注系统、非能动堆腔注水系统、过滤排放系统的个数和通往安全壳内部气空间的联通管线和单向阀组数相同。The object of the present invention is achieved in this way: an integrated heat release well is arranged in the middle and lower part of the interlayer gas space of the double-layer coagulated containment, the integrated heat release well is an annular pool surrounded by corrosion-resistant metal plates, and the upper part of the containment interlayer The inner containment wall of the air space is provided with at least one set of communication pipelines and one-way valves leading to the inner air space of the containment. Passive waste heat removal system, passive low-pressure safety injection system, passive reactor cavity water injection system, filter discharge system, containment rapid pressure relief system, automatic pressure relief system, passive waste heat removal system, passive low-pressure safety injection system, non-active The number of active reactor cavity water injection systems, filtration and discharge systems, and the number of communication pipelines leading to the gas space inside the containment and the number of one-way valve groups are the same.
本发明还包括这样一些结构特征:The present invention also includes such structural features:
1.还包括无时限非能动安全壳热量导出系统,无时限非能动安全壳热量导出系统的个数与通往安全壳内部气空间的联通管线和单向阀组数相同,无时限非能动安全壳热量导出系统包括外置自然通风式空冷机、冷管段、安全壳夹层PCS换热器、热管段,安全壳夹层PCS换热器布置在双层混凝土安全壳夹层中,外置自然通风式空冷机包括伞装挡板、进气口、排气口、渐缩管,过滤器,过滤器与冷管段连接,冷管段的端部与安全壳夹层PCS换热器的下端连接,热管段的一端与排气口连接、另一端与安全壳夹层PCS换热器的连接。1. It also includes the passive containment heat export system with no time limit. The number of passive containment heat export systems with no time limit is the same as the number of connecting pipelines and check valve groups leading to the gas space inside the containment. The passive safety vessel with no time limit The shell heat export system includes an external natural ventilation air cooler, cold pipe section, containment interlayer PCS heat exchanger, and heat pipe section. The containment interlayer PCS heat exchanger is arranged in the double-layer concrete containment interlayer, and the external natural ventilation air cooling The machine includes umbrella-mounted baffles, air inlets, exhaust ports, reducers, filters, and the filters are connected to the cold pipe section. The end of the cold pipe section is connected to the lower end of the containment interlayer PCS heat exchanger. It is connected to the exhaust port, and the other end is connected to the interlayer PCS heat exchanger of the containment vessel.
2.安全壳快速泄压系统包括设置在集成释热阱的下部水空间中的快速泄压管线,快速泄压管线的入口端穿过双层壳体的内壳伸入至安全壳内部气空间中。2. The rapid pressure relief system of the containment vessel includes a rapid pressure relief pipeline arranged in the lower water space of the integrated heat release trap. The inlet end of the rapid pressure relief pipeline passes through the inner shell of the double-layer shell and extends into the air space inside the containment vessel middle.
3.自动泄压系统包括自动泄压管线、设置在自动泄压管线上的自动泄压阀,自动泄压管线的入口端与位于主冷却剂回路上的稳压器的气腔连通、出口端伸入至集成释热阱的下部水空间中。3. The automatic pressure relief system includes an automatic pressure relief pipeline and an automatic pressure relief valve installed on the automatic pressure relief pipeline. Protrudes into the lower water space of the integrated heat trap.
4.非能动余热排出系统布置于反应堆主冷却剂回路上,包括依次连接的入口管线、非能动余热排出换热器、出口管线,入口管线和出口管线上均设置有阀门,入口管线连接蒸汽发生器前端的主冷却剂回路热管段,出口管线连接蒸汽发生器后端的主冷却剂回路冷管段,非能动余热排出换热器浸没于集成释热阱的下部水空间。4. The passive waste heat removal system is arranged on the main coolant circuit of the reactor, including the inlet pipeline, the passive waste heat removal heat exchanger, and the outlet pipeline connected in sequence. Valves are installed on the inlet pipeline and the outlet pipeline, and the inlet pipeline is connected to the steam generator. The heat pipe section of the main coolant circuit at the front end of the steam generator, the outlet pipeline is connected to the cold pipe section of the main coolant circuit at the rear end of the steam generator, and the passive waste heat discharge heat exchanger is immersed in the lower water space of the integrated heat release trap.
5.非能动低压安注系统包括非能动低压安注管线和单向阀,非能动低压安注管线的入口段位于集成释热阱的下部水空间中、出口段连接于反应堆压力容器的壁面,单向阀仅允许冷却水从集成释热阱下部水空间流向反应堆压力容器内部。5. The passive low-pressure safety injection system includes a passive low-pressure safety injection pipeline and a one-way valve. The inlet section of the passive low-pressure safety injection pipeline is located in the lower water space of the integrated heat release trap, and the outlet section is connected to the wall of the reactor pressure vessel. The one-way valve only allows the cooling water to flow from the lower water space of the integrated heat release trap to the inside of the reactor pressure vessel.
6.非能动堆腔注水系统包括堆腔注水管线、单向注水阀,堆腔注水管线的入口端浸没于集成释热阱下部水空间、出口端连接于由反应堆压力容器外壁面和保温层内壁面形成的夹层流道内。6. The passive reactor cavity water injection system includes a reactor cavity water injection pipeline and a one-way water injection valve. The inlet end of the reactor cavity water injection pipeline is immersed in the lower water space of the integrated heat release well, and the outlet end is connected to the outer wall of the reactor pressure vessel and the insulation layer. In the sandwich channel formed by the wall.
7.过滤排放系统包括一级水洗过滤系统和二级过滤排放系统,一级水洗过滤系统包括快速泄压管线、集成释热阱,二级过滤排放系统包括过滤排放阀、过滤排放管线、过滤排放装置,过滤排放管线的以端伸入安全壳夹层上部气空间中、另一端连接过滤排放装置。7. The filter discharge system includes a primary water washing filter system and a secondary filter discharge system. The primary water wash filter system includes a quick pressure relief pipeline and an integrated heat release trap. The secondary filter discharge system includes a filter discharge valve, a filter discharge pipeline, and a filter discharge One end of the filter discharge pipeline extends into the upper air space of the containment interlayer, and the other end is connected to the filter discharge device.
与现有技术相比,本发明的有益效果是:Compared with prior art, the beneficial effect of the present invention is:
1)本发明所设计的集成释热阱充分利用了双层混凝土安全壳夹层区域较大的空间体积,该紧凑型布置方案可避免在安全壳内部气空间布置内置换料水箱、非能动堆腔注水箱等众多冷却水源,可在保障反应堆固有安全性的基础上,有效简化反应堆系统布置。1) The integrated heat release trap designed in the present invention makes full use of the large space volume in the interlayer area of the double-layer concrete containment vessel. This compact layout scheme can avoid the arrangement of built-in refueling water tanks and passive reactor chambers in the gas space inside the containment vessel. Many cooling water sources such as water injection tanks can effectively simplify the layout of the reactor system on the basis of ensuring the inherent safety of the reactor.
2)在无时限非能动安全壳热量导出系统中设置的外置自然通风式空冷结构可避免在安全壳外部布置大型的换热水箱。相比于换热水箱,自然通风式空冷结构可实现无时限的安全壳热量导出,并且在船用或地震条件下,有良好的抗摇摆、抗震能力,此外,还具有环境污染小,设备寿命长,维护费用低等优点。2) The external natural ventilation air-cooling structure set in the timeless passive containment heat export system can avoid arranging large-scale heat exchange tanks outside the containment. Compared with the heat exchange tank, the naturally ventilated air-cooled structure can achieve unlimited time-limited heat export from the containment, and has good anti-sway and anti-seismic capabilities under marine or earthquake conditions. In addition, it also has less environmental pollution and long equipment life. , Low maintenance costs and other advantages.
3)安全壳夹层PCS换热器直接位于集成释热阱上方的设计可将冷凝水回收再利用。蒸汽冷凝后的水回落到集成释热阱内部水空间里,在保障换热器的换热能力的基础上,充分实现了冷凝水的回收再利用。3) The design of the containment interlayer PCS heat exchanger directly above the integrated heat release trap can recycle the condensed water for reuse. The condensed water falls back into the internal water space of the integrated heat release trap. On the basis of ensuring the heat exchange capacity of the heat exchanger, the condensed water is fully recovered and reused.
4)由安全壳快速泄压管线和集成释热阱构成的安全壳快速泄压系统可有效抵御反应堆大破口事故条件下在安全壳内形成的第一个压力峰值,从而避免了现有第三代压水堆核电技术中通过尽可能增大安全壳体积来缓解压力峰值的不足,有助于大幅减小安全壳体积并降低安全壳的建造成本。4) The containment rapid decompression system composed of the containment rapid decompression pipeline and the integrated heat release well can effectively resist the first pressure peak formed in the containment under the condition of the reactor large breach accident, thereby avoiding the existing third In the PWR nuclear power technology, increasing the volume of the containment as much as possible to alleviate the shortage of pressure peaks will help to greatly reduce the volume of the containment and reduce the construction cost of the containment.
5)位于双层混凝土安全壳夹层区域的集成释热阱可为自动泄压系统、非能动余热排出系统、非能动低压安注系统、非能动堆腔注水系统提供充足的冷却水源。释热阱中充足的冷却水以及外置自然通风式空冷结构可代替PCS外置水箱的存在。此外,将结构紧凑的集成释热阱与各类非能动排热系统相结合,能够在保障核电厂安全性的基础上提高核电厂的经济性。5) The integrated heat release well located in the interlayer area of the double-layer concrete containment can provide sufficient cooling water for the automatic pressure relief system, passive waste heat removal system, passive low pressure safety injection system, and passive reactor cavity water injection system. The sufficient cooling water in the heat release trap and the external natural ventilation air cooling structure can replace the existence of the PCS external water tank. In addition, the combination of compact integrated heat release sinks and various passive heat removal systems can improve the economics of nuclear power plants on the basis of ensuring the safety of nuclear power plants.
6)在无时限非能动安全壳热量导出系统中设置的安全壳夹层PCS换热器可有效应对多种事故工况。在蒸汽发射器二次侧事故条件下,安全壳PCS夹层换热器可与非能动余热排出系统联合排出反应堆内热量。在破口事故条件下,安全壳夹层PCS换热器与安全壳快速泄压系统联合作用可有效应对安全壳内的两个压力峰值。6) The containment interlayer PCS heat exchanger set in the timeless passive containment heat export system can effectively deal with various accident conditions. Under the accident condition of the secondary side of the steam emitter, the interlayer heat exchanger of the containment PCS can be combined with the passive waste heat removal system to discharge the heat in the reactor. Under breach accident conditions, the combination of containment interlayer PCS heat exchanger and containment rapid pressure relief system can effectively deal with the two pressure peaks in the containment.
7)通过在安全壳夹层上部气空间设置通往安全壳内部气空间的联通管线和单向阀,可以在确保各系统行使非能动安全功能的基础上有效平衡集成释热阱、安全壳夹层气空间、安全壳内部气空间之间的压力。7) By setting a connecting pipeline and a one-way valve leading to the inner gas space of the containment in the upper gas space of the containment interlayer, it is possible to effectively balance the integrated heat release well and the gas in the containment interlayer on the basis of ensuring that each system performs passive safety functions. The pressure between the space and the gas space inside the containment vessel.
8)安全壳快速泄压管线与集成释热阱水空间构成的一级水洗过滤系统在运行过程中可实现大多数可溶于水的放射性物质的居留,能够有效减轻二级过滤排放装置的过滤负荷。8) The first-stage water washing filter system composed of the containment rapid pressure relief pipeline and the integrated heat release well water space can realize the residence of most water-soluble radioactive substances during operation, and can effectively reduce the filtration rate of the second-stage filter discharge device. load.
附图说明Description of drawings
图1是本发明的整体结构图。Fig. 1 is the overall structure diagram of the present invention.
具体实施方式detailed description
下面结合附图与具体实施方式对本发明作进一步详细描述。The present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments.
由于现有的核电厂非能动安全系统设计方案中不同非能动系统有各自的冷却水箱/热阱,这既不利于安全壳内系统设备的简化,又没有充分利用安全壳内部的空间。此外,已有的安全壳非能动热量导出系统主要用于缓解破口事故条件下安全壳内的第二个压力峰值,而在第一个压力峰值的缓解方面尚未形成有效的方案。本发明基于双层混凝土安全壳夹层内的较大可用空间,在夹层气空间布置了集成释热阱,其可为多个非能动安全系统提供冷却水源,从而有助于简化系统布置。快速泄压管线与集成释热阱组成的安全壳快速泄压系统可有效抵御破口事故下安全壳内的第一个压力峰值,进而可显著减小安全壳体积并降低核电厂建造成本。Because different passive systems in the existing passive safety system design schemes of nuclear power plants have their own cooling water tanks/heat sinks, this is not conducive to the simplification of system equipment in the containment, and does not make full use of the space inside the containment. In addition, the existing containment passive heat removal system is mainly used to alleviate the second pressure peak in the containment under breach accident conditions, but there is no effective solution for the relief of the first pressure peak. Based on the large available space in the interlayer of the double-layer concrete containment vessel, the present invention arranges an integrated heat release trap in the air space of the interlayer, which can provide cooling water sources for multiple passive safety systems, thereby helping to simplify system layout. The rapid pressure relief system of the containment composed of the rapid pressure relief pipeline and the integrated heat release trap can effectively resist the first pressure peak in the containment under a breach accident, thereby significantly reducing the volume of the containment and reducing the construction cost of the nuclear power plant.
本发明提供一种具有集成释热阱的无时限非能动联合排热系统,包括集成释热阱、安全壳快速泄压系统、自动泄压系统、非能动余热排出系统、非能动低压安注系统、非能动堆腔注水系统、无时限非能动安全壳热量导出系统(PCS)以及过滤排放系统组成。The invention provides a timeless passive combined heat removal system with an integrated heat release trap, including an integrated heat release trap, a containment fast pressure relief system, an automatic pressure relief system, a passive waste heat discharge system, and a passive low pressure safety injection system , passive reactor cavity water injection system, timeless passive containment heat transfer system (PCS) and filter discharge system.
所述集成释热阱位于双层混凝的安全壳夹层气空间1的中下部,具体为由不锈钢板或其他耐腐蚀金属板2围成的大尺度环形水池,内部为水空间4,安全壳夹层上部气空间6中在内层安全壳壁面9上设置有通往安全壳内部气空间10的联通管线11和单向阀12。位于安全壳夹层上部气空间6的联通管线11和单向阀12仅允许气体由安全壳夹层气空间6排往安全壳内部气空间10。The integrated heat release well is located in the middle and lower part of the interlayer gas space 1 of the double-layer coagulated containment vessel, specifically a large-scale annular pool surrounded by stainless steel plates or other corrosion-resistant metal plates 2, the interior is a
所述安全壳快速泄压系统由快速泄压管线13和集成释热阱组成,泄压管线13的入口端位于安全壳内部气空间10,管线穿过内层安全壳壁面,伸入安全壳夹层上部气空间,出口端位于集成释热阱水空间4。The containment rapid pressure relief system is composed of a rapid
所述的自动泄压系统由自动泄压管线14、自动泄压阀15和集成释热阱组成,自动泄压管线14的入口端连接于稳压器气腔16、出口端位于集成释热阱水空间4,也可以这样描述:泄压管线入口端连接反应堆稳压器顶部并与稳压器内部气腔联通,出口端伸入集成释热阱并浸没于内部水空间,自动泄压阀安装于泄压管线受反应堆事故报警信号控制。The automatic pressure relief system is composed of an automatic
所述的非能动余热排出系统优选布置于反应堆主冷却剂回路17,由入口管线18、阀门19,非能动余热排出换热器20,以及出口管线21、阀门22组成,入口管线位于蒸汽发生器前端的主冷却剂回路热管段,出口管线位于蒸汽发生器后端的主冷却剂回路冷管段,非能动余热排出换热器浸没于集成释热阱内部水空间,具体说是:入口管线18连接于一次侧冷却水回路热管段23,出口管线21连接于一次侧冷却水回路冷管段24。所述的非能动余热排出系统也可按相似的布置方式应用于蒸汽发生器二次侧。The passive waste heat removal system is preferably arranged in the reactor main coolant circuit 17, and is composed of an
所述的非能动低压安注系统由集成释热阱、非能动低压安注管线25和单向阀26组成,非能动低压安注管线25的入口段位于集成释热阱水空间4,非能动低压安注管线25的出口段连接于反应堆压力容器27壁面,单向阀26仅允许冷却水从集成释热阱水空间4流向反应堆压力容器27内部。The passive low-pressure safety injection system is composed of an integrated heat release well, a passive low-pressure safety injection pipeline 25 and a check valve 26. The entrance section of the passive low-pressure safety injection pipeline 25 is located in the
所述的非能动堆腔注水系统由集成释热阱、堆腔注水管线28以及单向注水阀29组成,堆腔注水管线28入口端浸没于集成释热阱水空间4,出口端连接于由压力容器外壁面30和保温层内壁面31形成的夹层流道32内。The passive reactor cavity water injection system is composed of an integrated heat release well, a reactor cavity
所述的无时限非能动安全壳热量导出系统包括外置自然通风式空冷机33、冷管段34、安全壳夹层PCS换热器35、热管段37。安全壳夹层PCS换热器35优选采取环形布置在双层混凝土安全壳夹层中。The timeless passive containment heat export system includes an external natural
所述的外置自然通风式空冷机33包括伞装挡板36、进气口5、排气口3、渐缩管39,过滤器38。伞装挡板36在雨雪天气可有效保护空冷结构,过滤器38可用于防止外界生物、杂质进入空冷结构33。The external natural
所述的过滤排放系统由安全壳快速泄压管线13、集成释热阱、过滤排放阀40、过滤排放管线41以及过滤排放装置42组成,其中,过滤排放管线41的入口端伸入安全壳夹层上部气空间6,另一端连接过滤排放装置42,快速泄压管线13与集成释热阱构成一级水洗过滤系统,过滤排放阀40、过滤排放管线41以及过滤排放装置42构成二级过滤排放系统。The filter discharge system is composed of containment rapid
本发明主要用于缓解核电厂运行过程可能发生的主冷却水回路破口事故、主蒸汽管道破口事故、蒸汽发生器二次侧给水事故等。在反应堆发生失水事故尤其是小破口事故条件下,反应堆主冷却剂回路需进行快速降压以便外部冷却水在低压条件下非能动的注入反应堆主冷却剂回路17。该类事故条件下,位于主冷却剂回路稳压器43上部的自动泄压系统启动运行。在事故触发信号的作用下,自动泄压阀16开启,稳压器气空间16的高温蒸汽通过泄压管线14通入集成释热阱水空间4完成主冷却剂回路的泄压过程。集成释热阱中大量的冷却水可有效容纳自动泄压过程所释放的能量。当反应堆主冷却剂回路17内压力降低到接近常压时,非能动低压安注系统启动运行,集成释热阱水空间4中的冷却水通过低压安注管线25通入反应堆压力容器27,以确保反应堆堆芯处于淹没状态。The invention is mainly used for mitigating the breach accidents of the main cooling water circuit, the breach accident of the main steam pipeline, the water supply accident of the secondary side of the steam generator and the like which may occur in the operation process of the nuclear power plant. In the event of a loss of water accident in the reactor, especially a small breach accident, the reactor main coolant circuit needs to be rapidly depressurized so that the external cooling water can be passively injected into the reactor main coolant circuit 17 under low pressure. Under such accident conditions, the automatic pressure relief system located on the upper part of the main coolant circuit voltage stabilizer 43 starts to operate. Under the action of the accident trigger signal, the automatic pressure relief valve 16 is opened, and the high-temperature steam in the gas space 16 of the pressurizer is passed through the
在发生熔堆事故条件下,非能动堆腔注水系统启动运行,单向阀29自动开启,集成释热阱水空间4中的冷却水通过堆腔注水管线29流入由压力容器外壁面30和保温层内壁面31形成的夹层流道32内,以冷却压力容器27防止其熔穿。In the event of a fusion reactor accident, the passive reactor cavity water injection system starts to operate, the one-way valve 29 is automatically opened, and the cooling water in the
当蒸汽发生器44发生主蒸汽管破口事故或给水系统工作异常时,蒸汽发生器二次侧将失去排热能力。为在该类事故条件下确保反应堆主冷却水回路17热量的有效导出,本发明设置的非能动余热排出系统启动运行。非能动余热排出系统隔离阀19、22在事故信号的触发下自动开启,反应堆主冷却水回路热管段23的冷却剂通过入口管线18进入非能动余热排出系统换热器20,冷却后通过出口管线21返回主冷却剂回路17。其中,非能动余热排出系统换热器20浸没于集成释热阱的水空间4,集成释热阱中充足的水装量可为非能动余热排出系统的运行提供长期热阱。When the
当反应堆发生大破口失水事故时,将有大量高温蒸汽喷放进入安全壳气空间10,导致安全壳内压力的升高。根据事故发展的进程,安全壳内部气空间将形成2个压力峰值,一是破口喷放初期的几十秒内在安全壳内形成的幅值较高的第一个压力峰值,二是堆芯再淹没后进行长期冷却过程中所形成的第二个压力峰值。When a large breach loss of water accident occurs in the reactor, a large amount of high-temperature steam will be sprayed into the gas space 10 of the containment vessel, resulting in an increase in the pressure inside the containment vessel. According to the progress of the accident, two pressure peaks will be formed in the gas space inside the containment vessel. One is the first pressure peak with a higher amplitude formed in the containment within tens of seconds at the initial stage of breach blowout, and the other is the pressure peak in the core. The second pressure peak formed during the long cooling process after reflooding.
本发明通过由快速泄压管线13和集成释热阱组成的快速泄压系统来缓解第一个压力峰值。在大破口失水事故条件下,安全壳内10的高压蒸汽-空气混合气体将通过快速泄压管线13进入集成释热阱水空间4,冷却水通过凝结混合气体中的蒸汽以有效缓解安全壳第一个压力峰值。为在事故长期发展过程中平衡集成释热阱与其它气体区域间的压力,安全壳夹层上部气空间5的内层安全壳壁面9上设置有通往安全壳内部气空间10的联通管线11和单向阀12。The present invention relieves the first pressure peak by means of a rapid pressure relief system consisting of a rapid
针对第二个压力峰值,本发明设置了由外置自然通风式空冷结构33、冷管段34、安全壳夹层PCS换热器35、热管段37组成的无时限非能动安全壳热量导出系统。其中,安全壳夹层PCS换热器35布置于内层安全壳9与外层安全壳45的夹层气空间6。For the second peak pressure, the present invention sets a timeless passive containment heat export system consisting of an external natural ventilation air-
事故长期发展过程中,由于安全壳外部采用自然通风式空冷结构33,可为安全壳提供无时限的热量导出。在安全壳气空间10达到较高压力时,气体可通过快速泄压管线13进入集成释热阱水空间4。从而气体进入安全壳夹层气空间6,所携带的热量通过安全壳夹层PCS换热器35导出,冷凝后的水回落到集成释热阱中,可实现冷凝水的回收再利用。During the long-term development of the accident, since the outside of the containment adopts a natural ventilation air-cooling structure33, it can provide unlimited heat export for the containment. When the containment gas space 10 reaches a higher pressure, the gas can enter the
在安全壳气空间10的降压阶段,安全壳夹层气空间6的压力较高。当安全壳夹层气空间6与安全壳内部气空间10形成一定的压差时,安全壳夹层内的气体通过安全壳夹层上部气空间6的联通管线11和单向阀12排往安全壳内部气空间10,最终实现安全壳夹层气空间6和安全壳内部气空间10的压力平衡。During the depressurization stage of the containment gas space 10, the pressure of the containment interlayer gas space 6 is relatively high. When a certain pressure difference is formed between the containment interlayer gas space 6 and the containment internal gas space 10, the gas in the containment interlayer is discharged to the containment internal gas through the communication pipeline 11 and the check valve 12 in the upper gas space 6 of the containment interlayer. The space 10 finally realizes the pressure balance between the gas space 6 in the interlayer of the containment and the gas space 10 inside the containment.
在非预期的事故条件下导致安全壳气空间10内部的压力过高时,在安全壳高压信号的出发下过滤排放阀40开启,安全壳过滤排放系统启动运行。安全壳气空间10内部带有放射性物质的高温高压气体首先进入由快速泄压管线13与集成释热阱构成一级水洗过滤系统,这一过程使大多数可溶于水的放射性物质居留在集成释热阱的水空间4。经一级水洗过滤后,混合气体由集成释热阱进入安全壳夹层气空间6,之后通过过滤排放管线41进入过滤排放装置42,完成放射性过滤的气体最终排放至外界环境。When the pressure inside the containment gas space 10 is too high due to unexpected accident conditions, the filter and discharge
综上,本发明的目的在于提供一种具有集成释热阱的无时限非能动联合排热系统,其主要由集成释热阱、安全壳快速泄压系统、自动泄压系统、非能动余热排出系统、非能动低压安注系统、非能动堆腔注水系统、无时限非能动安全壳热量导出系统(PCS)以及过滤排放系统组成。集成释热阱作为多种反应堆事故下的关键冷源,布置于双层混凝土安全壳环形夹层中下部,底部和侧面采用不锈钢板围成大尺度环形水池。无时限非能动安全壳热量导出系统由外置自然通风式空冷结构、内置在双层混凝土安全壳夹层上部气空间的热交换器以及进出口管线组成。在反应堆发生失水事故和蒸汽发生器二次侧失效条件下,集成释热阱可为自动泄压系统和非能动余热排出系统换热器提供排热热阱,并为非能动低压安注系统和非能动堆腔注水系统提供充足的冷却水源。在大破口失水事故引发的严重事故条件下,集成释热阱结合安全壳快速泄压管线可有效抵御安全壳内第一个压力峰值,与无时限非能动安全壳热量导出系统和过滤排放装置联合作用可有效缓解安全壳内第二个压力峰值并实现放射性的居留。集成释热阱以及无时限非能动安全壳热量导出系统的设计充分利用了双层混凝土安全壳的夹层空间,可为各类非能动安全系统提供充足冷源,将有助于大幅缩减安全壳气空间体积,并且抗震能力强,可无时限的进行安全壳内热量导出,进而为提高先进核动力电厂的经济性和非能动安全性提供可行方案。In summary, the purpose of the present invention is to provide a timeless passive combined heat removal system with an integrated heat release trap, which is mainly composed of an integrated heat release trap, a containment rapid pressure relief system, an automatic pressure relief system, and passive waste heat discharge System, passive low-pressure safety injection system, passive reactor cavity water injection system, timeless passive containment heat export system (PCS) and filter discharge system. The integrated heat release well, as the key cold source under various reactor accidents, is arranged in the middle and lower part of the annular interlayer of the double-layer concrete containment, and the bottom and sides are surrounded by stainless steel plates to form a large-scale annular pool. The timeless passive containment heat export system consists of an external natural ventilation air-cooling structure, a heat exchanger built in the upper air space of the double-layer concrete containment interlayer, and inlet and outlet pipelines. In the event of a loss of water accident in the reactor and failure of the secondary side of the steam generator, the integrated heat sink can provide a heat sink for the automatic pressure relief system and the heat exchanger of the passive waste heat removal system, and provide a heat sink for the passive low pressure safety injection system. And the passive reactor cavity water injection system provides sufficient cooling water source. Under severe accident conditions caused by a large breach loss of water accident, the integrated heat release well combined with the rapid pressure relief pipeline of the containment can effectively resist the first pressure peak in the containment, combined with the timeless passive containment heat export system and filter discharge device The combined action can effectively relieve the second pressure peak in the containment and achieve radioactive containment. The design of the integrated heat release trap and the timeless passive containment heat export system makes full use of the interlayer space of the double-layer concrete containment, which can provide sufficient cold sources for various passive safety systems, and will help greatly reduce the containment gas pressure. The space is large and the anti-seismic ability is strong, and the heat in the containment can be exported without a time limit, thereby providing a feasible solution for improving the economy and passive safety of advanced nuclear power plants.
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Citations (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN101154472A (en) * | 2006-09-29 | 2008-04-02 | 中国核动力研究设计院 | Integrated low-temperature nuclear heating reactor |
CN103295656A (en) * | 2012-02-29 | 2013-09-11 | 上海核工程研究设计院 | Diversified engineered safety system for nuclear reactor |
EP2680272A2 (en) * | 2012-06-29 | 2014-01-01 | Kabushiki Kaisha Toshiba | Nuclear power plant and passive containment cooling system |
CA2830874A1 (en) * | 2012-10-24 | 2014-04-24 | Hitachi-Ge Nuclear Energy, Ltd. | Passive residual heat removal system and nuclear power plant equipment |
CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
CN104361914A (en) * | 2014-11-19 | 2015-02-18 | 中科华核电技术研究院有限公司 | Passive safe cooling system |
CN204178729U (en) * | 2014-07-24 | 2015-02-25 | 哈尔滨工程大学 | A kind of long-term passive containment thermal conduction system |
CN104979024A (en) * | 2015-05-20 | 2015-10-14 | 中国核动力研究设计院 | Passive pressure-relief, water-injection and cooling system for floating nuclear power plant and operation method therefor |
CN105957564A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Pressure suppression and safe injection system |
CN106104701A (en) * | 2014-07-24 | 2016-11-09 | 哈尔滨工程大学 | Containment cooling system and containment combine cooling system with reactor pressure vessel |
CN109659043A (en) * | 2017-10-10 | 2019-04-19 | 中国船舶重工集团公司第七〇九研究所 | A kind of nuclear constrain test platform in ocean |
WO2020050519A1 (en) * | 2018-09-04 | 2020-03-12 | Korea Atomic Energy Research Institute | Nuclear reactor long-term cooling system and nuclear plant having the same |
Family Cites Families (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR101389276B1 (en) * | 2012-07-13 | 2014-04-25 | 한국원자력연구원 | Passive Safety System of Integral Reactor |
CN106898389A (en) * | 2015-12-21 | 2017-06-27 | 中国核动力研究设计院 | A kind of constrain cooling system of inherently safe containment |
CN106251916B (en) * | 2016-08-31 | 2018-01-23 | 长江勘测规划设计研究有限责任公司 | A kind of underground nuclear power station cavern type double containment |
JP2018072068A (en) * | 2016-10-26 | 2018-05-10 | 日立Geニュークリア・エナジー株式会社 | Reactor vessel and reactor power plant |
CN107170493B (en) * | 2017-04-27 | 2020-12-18 | 中国核电工程有限公司 | Passive containment heat exporting system |
CN107799188A (en) * | 2017-10-30 | 2018-03-13 | 上海核工程研究设计院有限公司 | A kind of containment pressure supression system |
CN207624391U (en) * | 2017-12-08 | 2018-07-17 | 中国船舶重工集团公司第七一九研究所 | A kind of constrain system and the shared heat derivation device of residual heat removal system |
CN108335764B (en) * | 2018-01-24 | 2020-01-21 | 中广核研究院有限公司 | Small-size spent fuel cooling and clean system that piles |
CN108346475A (en) * | 2018-01-24 | 2018-07-31 | 中广核研究院有限公司 | A kind of passive constrain system of small-sized heap containment |
CN108281204A (en) * | 2018-01-24 | 2018-07-13 | 中广核研究院有限公司 | A kind of small-sized heap peace note recirculating system |
CN108492892B (en) * | 2018-02-28 | 2020-04-07 | 哈尔滨工程大学 | Built-in containment filtering and discharging system |
CN108520785B (en) * | 2018-06-19 | 2023-07-28 | 中国科学院上海应用物理研究所 | Passive waste heat discharging system and waste heat discharging method for molten salt reactor |
CN108877966B (en) * | 2018-06-25 | 2021-06-01 | 哈尔滨工程大学 | Closed passive containment cooling system for floating nuclear power station |
CN111128414B (en) * | 2019-12-31 | 2022-07-26 | 中国核动力研究设计院 | Active and passive combined safety system and method for nuclear power plant |
-
2020
- 2020-09-15 CN CN202010965743.8A patent/CN112053791B/en active Active
Patent Citations (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN101154472A (en) * | 2006-09-29 | 2008-04-02 | 中国核动力研究设计院 | Integrated low-temperature nuclear heating reactor |
CN103295656A (en) * | 2012-02-29 | 2013-09-11 | 上海核工程研究设计院 | Diversified engineered safety system for nuclear reactor |
EP2680272A2 (en) * | 2012-06-29 | 2014-01-01 | Kabushiki Kaisha Toshiba | Nuclear power plant and passive containment cooling system |
CA2830874A1 (en) * | 2012-10-24 | 2014-04-24 | Hitachi-Ge Nuclear Energy, Ltd. | Passive residual heat removal system and nuclear power plant equipment |
CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
CN204178729U (en) * | 2014-07-24 | 2015-02-25 | 哈尔滨工程大学 | A kind of long-term passive containment thermal conduction system |
CN106104701A (en) * | 2014-07-24 | 2016-11-09 | 哈尔滨工程大学 | Containment cooling system and containment combine cooling system with reactor pressure vessel |
CN104361914A (en) * | 2014-11-19 | 2015-02-18 | 中科华核电技术研究院有限公司 | Passive safe cooling system |
CN104979024A (en) * | 2015-05-20 | 2015-10-14 | 中国核动力研究设计院 | Passive pressure-relief, water-injection and cooling system for floating nuclear power plant and operation method therefor |
CN105957564A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Pressure suppression and safe injection system |
CN109659043A (en) * | 2017-10-10 | 2019-04-19 | 中国船舶重工集团公司第七〇九研究所 | A kind of nuclear constrain test platform in ocean |
WO2020050519A1 (en) * | 2018-09-04 | 2020-03-12 | Korea Atomic Energy Research Institute | Nuclear reactor long-term cooling system and nuclear plant having the same |
Non-Patent Citations (3)
Title |
---|
ACP100+失水事故应对策略研究;曾未等;《核动力工程》;20171215(第06期);第76-79页 * |
压水堆核电厂余热排出系统设计中一些安全问题的探讨;依岩等;《核安全》;20060330(第01期);第52-56页 * |
非能动余热排出换热器冷凝换热性能研究;王开元等;《原子能科学技术》;20151020(第10期);第30-35页 * |
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