CN112071454A - Passive combined heat removal system with integrated heat release trap - Google Patents
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Abstract
本发明提供一种具有集成释热阱的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,集成释热阱的顶部壁面设置有至少一组的连通集成释热阱与安全壳内部气空间的管路和单向阀,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。本发明简化核电厂反应堆系统布置、缩小安全壳体积,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 passive combined heat removal system with an integrated heat release trap. An integrated heat release well is arranged in the middle and lower part of the double-layer coagulation containment interlayer gas space. The integrated heat release well is surrounded by a corrosion-resistant metal plate. The top wall of the integrated heat release trap is provided with at least one set of pipelines and one-way valves connecting the integrated heat release trap and the air space inside the containment, and the integrated heat release trap is connected to the containment for 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 simplifies the arrangement of the nuclear power plant reactor system, reduces the containment volume, and provides a feasible solution for improving the economy and passive safety of an advanced nuclear power plant.
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 passive combined heat removal system with an integrated heat release trap.
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 commercialization of nuclear energy in the 1960s and 1970s, it has provided human beings with clean and efficient energy for a long time. Due to the potential radioactive risks during 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 serious accidents in the field of nuclear energy: one 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 operation errors are likely to cause serious accidents in the reactor; active safety facilities have great potential safety hazards under the condition of a power outage accident in the whole plant. How to use the passive safety system to export the residual 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 research and development of the third-generation nuclear power plant.
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 No. 1" with completely independent property rights has innovatively introduced the design concept of combining active and passive for potential reactor accidents. In terms of passive safety system, passive safety injection system, passive residual heat discharge system and passive reactor cavity water injection system are provided for the main coolant circuit and the secondary side. For the last safety barrier of the nuclear power plant, the double-layer concrete containment is equipped with a passive containment heat transfer system. The coordinated operation of these systems can effectively resist the power failure of the whole 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。Regarding advanced nuclear energy technology, existing invention patents disclose some passive safety systems. Among them, the patents with publication numbers CN111128414A and CN111383782A provide several passive safety systems, including passive containment heat removal systems, secondary side passive residual heat removal systems, and passive safety injection systems, etc. The authorization number is CN209149827U, the publication number A passive secondary side waste heat discharge system is provided for the patent CN110021447A, and the patents with publication numbers CN110400644A and CN106024077A respectively disclose a passive containment heat discharge system. The feature of these patents is that they mainly focus on the layout of each passive system, and do not consider the relationship between different passive safety systems in the 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 of the containment, which is not conducive to the simplification of the complex circuit of the nuclear power plant. Reduction in 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 the heat dissipation of the containment, according to the development process of the accident, there will be two pressure peaks in the air space inside the containment. The second pressure peak is the second pressure peak formed during the long-term cooling process after the core is submerged. Regarding the solution for the pressure relief of the containment gas space, the published patents are mainly aimed at the second pressure peak, and there is no effective solution for alleviating the first pressure peak 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两点: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。It can be seen that the further development of existing passive safety systems is mainly limited to the following two points: one is how to effectively deal with the first pressure peak of a large breach accident with a small containment volume; the other is how to effectively integrate different Heat sinks for passive systems to simplify system layout and reduce equipment redundancy.
因此,有必要发明一种具有集成释热阱的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、降低PCS外置换热水箱体积与水装量,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 passive combined heat removal system with integrated heat release trap to simplify the layout of the reactor system, reduce the volume of the containment, reduce the volume and water capacity of the replacement hot water tank outside the PCS, and ultimately provide an advanced nuclear power plant. The economy and passive safety provide a feasible solution.
发明内容SUMMARY OF THE INVENTION
本发明的目的是为了提供一种具有集成释热阱的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 passive combined heat removal system with an integrated heat release trap, which is used to simplify the layout of the nuclear power plant reactor system, reduce the volume of the containment, and improve the economy and passive safety of advanced nuclear power plants. Provide feasible solutions.
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,集成释热阱的顶部壁面设置有至少一组的连通集成释热阱与安全壳内部气空间的管路和单向阀,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连通集成释热阱与安全壳内部气空间的管路和单向阀组数相同。The purpose of the present invention is to achieve this: an integrated heat release trap is arranged in the middle and lower part of the double-layer coagulated containment interlayer gas space, and the integrated heat release well is an annular pool surrounded by corrosion-resistant metal plates. The top wall is provided with at least one set of pipelines and one-way valves connecting the integrated heat release trap and the air space inside the containment, and the integrated heat release trap is connected with the containment rapid pressure relief system, automatic pressure relief system, 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 residual heat discharge system, passive low pressure safety injection system, passive reactor The number of cavity water injection systems, filter and discharge systems, and the number of pipelines and one-way valve groups connecting the integrated heat release trap and the air space inside the containment 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.还包括非能动安全壳热量导出系统,非能动安全壳热量导出系统的数量和连通集成释热阱与安全壳内部气空间的管路和单向阀的组数相同,非能动安全壳热量导出系统包括分别设置在双层混凝的安全壳夹层中、安全壳内部中的换热器,每个换热器入口端连接有进口隔离阀和冷管段、出口端连接有出口隔离阀和热管段,每个冷管段的端部和热管段的端部均与安全壳外置换热水箱连通。1. It also includes the passive containment heat export system. The number of passive containment heat export systems and the number of pipelines and one-way valves connecting the integrated heat release trap and the air space inside the containment are the same. The passive containment heat The export system includes heat exchangers respectively arranged in the double-layer coagulation containment interlayer and inside the containment. The inlet end of each heat exchanger is connected with an inlet isolation valve and a cold pipe section, and the outlet end is connected with an outlet isolation valve and a heat pipe. The end of each cold pipe section and the end of the hot pipe section are in communication with the replacement hot water tank outside the containment.
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 includes a rapid pressure relief line arranged in the lower water space of the integrated heat release trap, and the inlet end of the quick pressure relief line extends through the inner shell of the double-layer shell into the inner air space of the containment 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 line and an automatic pressure relief valve arranged on the automatic pressure relief line. The inlet end of the automatic pressure relief line is communicated with the air chamber of the regulator located on the main coolant circuit, and the outlet end 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 main coolant circuit heat pipe section at the front end of the steam generator, the outlet pipeline is connected to the main coolant circuit cold pipe section 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 well.
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 passive low-pressure safety-injection pipeline and 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 cooling water to flow from the lower water space of the integrated heat trap to the interior 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 the reactor cavity water injection pipeline and 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 surface of the reactor pressure vessel and the insulation layer. In the interlayer flow 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 filtration and discharge system includes a primary water washing filtration system and a secondary filtration and discharge system. The primary water washing and filtration system includes a rapid pressure relief line and an integrated heat release trap. One end of the filtering and discharging pipeline extends into the upper air space of the containment interlayer, and the other end is connected to the filtering and discharging device.
与现有技术相比,本发明的有益效果是:Compared with the prior art, the beneficial effects of the present invention are:
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 of the interlayer area of the double-layer concrete containment. This compact layout scheme can avoid the replacement of the material water tank and the passive reactor cavity in the air space arrangement inside the containment. 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)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。2) The containment rapid pressure relief system composed of the containment rapid pressure relief pipeline and the integrated heat release trap can effectively resist the first pressure peak formed in the containment under the condition of the large reactor rupture accident, thus avoiding the existing third pressure. In the generation of pressurized water reactor nuclear power technology, by maximizing the volume of the containment to alleviate the shortage of pressure peaks, it is helpful to greatly reduce the volume of the containment and reduce the construction cost of the containment.
3)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可切实减小PCS外置水箱的体积和蓄水量。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。3) The integrated heat release trap located in the interlayer area of the double-layer concrete containment can provide sufficient cooling water source for the automatic pressure relief system, passive residual heat removal system, passive low-pressure safety injection system, and passive reactor cavity water injection system. Sufficient cooling water in the heat release trap can effectively reduce the volume and water storage capacity of the PCS external water tank. In addition, the combination of the compact integrated heat release trap and various passive heat removal systems can improve the economy of the nuclear power plant on the basis of ensuring the safety of the nuclear power plant.
4)在非能动安全壳热量导出系统中设置的安全壳内置PCS换热器和安全壳夹层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,安全壳内置PCS换热器、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。4) The containment built-in PCS heat exchanger and the containment interlayer PCS heat exchanger set in the passive containment heat export system can effectively deal with various accident conditions. Under the accident conditions on the secondary side of the steam launcher, the containment PCS interlayer heat exchanger can be combined with the passive waste heat removal system to discharge the heat in the reactor. Under the condition of breach accident, the combined effect of the built-in PCS heat exchanger in the containment, the PCS interlayer heat exchanger in the containment and the rapid pressure relief system of the containment can effectively cope with the two pressure peaks in the containment.
5)通过在释热阱气空间顶部壁面设置通往安全壳夹层上部气空间的联通管线和单向阀,以及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。5) By setting the connecting pipeline and one-way valve leading to the upper gas space of the containment interlayer on the top wall of the heat-releasing trap gas space, and setting the connecting pipeline and one-way valve leading to the inner gas space of the containment in the upper gas space of the containment interlayer The valve can effectively balance the pressure between the integrated heat release trap, the interlayer gas space of the containment, and the gas space inside the containment on the basis of ensuring the passive safety function of each system.
6)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。6) The primary water washing filtration system composed of the rapid pressure relief pipeline of the containment and the integrated heat release trap water space can realize the residence of most water-soluble radioactive substances during operation, which can effectively reduce the filtration of the secondary filtration discharge device. load.
附图说明Description of drawings
图1是本发明的整体结构示意图;Fig. 1 is the overall structure schematic diagram of the present invention;
图2是本发明的串联运行模式示意图;2 is a schematic diagram of a series operation mode of the present invention;
图3是本发明的单回路单独运行示意图。FIG. 3 is a schematic diagram of the single-circuit independent operation of the present invention.
具体实施方式Detailed ways
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 described in further detail below with reference to 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。Since different passive systems in the existing passive safety system design scheme 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 the space inside the containment is not fully utilized. In addition, the existing passive heat transfer systems for containment are mainly used to relieve the second pressure peak in the containment under the condition of a breach accident, but there is no effective solution for mitigating the first pressure peak. The invention is based on the large available space in the interlayer of the double-layer concrete containment, and an integrated heat release trap is arranged in the interlayer gas space, which can provide cooling water sources for multiple passive safety systems, thereby helping to simplify the 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 the rupture accident, which can significantly reduce the volume of the containment and reduce the construction cost of the nuclear power plant.
本发明提供一种具有集成释热阱的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、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 passive combined heat removal system with an integrated heat release trap, including an integrated heat release well, a rapid pressure relief system for a containment, an automatic pressure relief system, a passive residual heat discharge system, a passive low-pressure safety injection system, a non-active It consists of an active reactor cavity water injection system, a passive containment heat transfer system (PCS) and a 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,内部分为上部气空间3和下部水空间4,释热阱的上部气空间3顶部壁面5设置有通往安全壳夹层上部气空间6的联通管线7和单向阀8,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。位于气空间顶部的联通管线7和单向阀8仅允许气体由集成释热阱气空间3排往安全壳夹层上部气空间6,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 trap is located in the middle and lower part of the double-layer coagulated containment interlayer gas space 1, and is specifically a large-scale annular pool surrounded by stainless steel plates or other corrosion-
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,伸入集成释热阱气空间,出口端位于集成释热阱下部水空间4。The rapid pressure relief system of the containment 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下部水空间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 pressure relief line 14, an automatic pressure relief valve 15 and an integrated heat release trap. The inlet end of the automatic pressure relief line 14 is connected to the air chamber 16 of the pressure regulator, and the outlet end is located in the integrated heat release trap.
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 consists 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 trap, a passive low pressure
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,出口端连接于由反应堆压力容器外壁面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
所述的非能动安全壳热量导出系统包括安全壳外置换热水箱33、冷管段34、安全壳夹层PCS换热器35、安全壳内置PCS换热器36、热管段37、进口隔离阀38、出口隔离阀39。安全壳内置PCS换热器36和安全壳夹层PCS换热器35可与PCS冷管段34、热管段37构成并联运行模式或串联运行模式。安全壳内置PCS换热器36可以与冷热管段34、37形成单回路单独运行,也可以和安全壳夹层换热器35组成双回路联合运行。The passive containment heat export system includes a replacement
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 described filter and discharge system is composed of the 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15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 alleviating the main cooling water circuit rupture accident, the main steam pipeline rupture accident, the secondary side water supply accident of the steam generator and the like that may occur during the operation of the nuclear power plant. In the event of a water loss 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 conditions. Under such accident conditions, the automatic pressure relief system located on the upper part of the main coolant circuit regulator 43 starts operation. Under the action of the accident trigger signal, the automatic pressure relief valve 15 is opened, and the high-temperature steam in the gas space 16 of the pressurizer passes through the pressure relief line 14 into the integrated heat
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。Under the condition of a fusion reactor accident, the passive reactor cavity water injection system starts operation, the one-
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 water loss accident occurs in the reactor, a large amount of high-temperature steam will be ejected into the containment gas space 10, resulting in an increase in the pressure in the containment. According to the development process of the accident, there will be two pressure peaks in the gas space inside the containment. One is the first pressure peak with higher amplitude formed in the containment within a few tens of seconds in the initial stage of the burst ejection, and the other is the core. The second pressure peak formed during long-term cooling after re-submersion.
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,释热阱气空间3顶部壁面5设置有通往安全壳夹层上部气空间6的联通管线7和单向阀8,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 alleviates 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,本发明设置了由安全壳外置换热水箱33、冷管段34、安全壳夹层PCS换热器35、安全壳内置PCS换热器36、热管段37、进口隔离阀38、出口隔离阀39组成的非能动安全壳热量导出系统。其中,安全壳内置换热器36布置于安全壳内部气空间10,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,安全壳内置PCS换热器36和安全壳夹层PCS换热器35可与PCS冷热管段34、37构成并联运行模式(如图1)或串联运行模式(如图2)。安全壳内置PCS换热器36可以与冷热管段34、37形成单回路单独运行(如图3),也可以和安全壳夹层换热器35组成双回路联合运行(如图1)。For the second pressure peak, the present invention provides a replacement
事故长期发展过程中,在安全壳气空间10的增压阶段,安全壳内置PCS换热器36通过凝结安全壳内气空间10中的蒸汽以缓解安全壳内压力的升高。在安全壳气空间10较高压力的作用下,气体通过快速泄压管线13进入集成释热阱水空间4。当集成释热阱气空间3与安全壳夹层气空间6形成一定的压差后,气空间混合气体通过释热阱气空间3顶部壁面的联通管线7和单向阀8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。During the long-term development of the accident, during the pressurization stage of the containment gas space 10 , 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。同理,在一定压差的作用下,集成释热阱气空间3中的气体通过位于集成释热阱气空间3顶部壁面的联通管线7和单向阀8进入安全壳夹层气空间6,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 gas space 6 of the containment interlayer and the gas space 10 inside the containment, the gas in the interlayer of the containment is discharged to the gas inside the containment through the communication pipeline 11 and the one-way valve 12 of the gas space 6 in the upper part of the containment interlayer. Space 10. In the same way, under the action of a certain pressure difference, the gas in the integrated heat release trap gas space 3 enters the containment interlayer gas space 6 through the communication pipeline 7 and the one-way valve 8 located on the top wall of the integrated heat release trap gas space 3, and finally. The pressure balance between the containment interlayer gas space 6 and the containment inner gas space 10 is achieved.
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,混合气体由位于集成释热阱气空间3顶部壁面5的联通管线7和单向阀8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 under unexpected accident conditions, the
综上,本发明的目的在于提供一种具有集成释热阱的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、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,四周采用不锈钢板围成大尺度环形水池,内部分为下部水空间和上部气空间。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PCS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、减小PCS外置换热水箱体积与水装量,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。To sum up, the purpose of the present invention is to provide a passive combined heat removal system with an integrated heat release trap, which mainly consists of an integrated heat release well, a rapid pressure relief system for a containment, an automatic pressure relief system, a passive residual heat discharge system, It consists of passive low pressure safety injection system, passive reactor cavity water injection system, passive containment heat transfer system (PCS) and filter discharge system. As the key cold source in various reactor accidents, the integrated heat trap is arranged in the middle and lower part of the annular interlayer of the double-layer concrete containment, surrounded by stainless steel plates to form a large-scale annular pool, and the interior is divided into a lower water space and an upper air space. In the event of a water loss accident in the reactor and the failure of the secondary side of the steam generator, the integrated heat release trap can provide a heat release heat sink for the heat exchanger of the automatic pressure relief system and the passive waste heat removal system, and provide a heat sink for the passive low pressure safety injection system. and passive reactor cavity water injection system to provide sufficient cooling water source. Under the severe accident conditions caused by the large break water loss accident, the integrated heat release trap combined with the rapid pressure relief line of the containment can effectively resist the first pressure peak in the containment, and the combination with the PCS system and the filter discharge device can effectively relieve the containment within the second pressure peak and achieve radioactive residency. The design of the integrated heat trap makes full use of the interlayer space of the double-layer concrete containment, which can provide sufficient cold source for various passive safety systems, which will help to greatly reduce the volume of the containment gas space and reduce the replacement of hot water outside the PCS. The volume of the tank and the amount of water in the tank provide a feasible solution for improving the economy and passive safety of advanced nuclear power plants.
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Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111912641A (en) * | 2020-07-15 | 2020-11-10 | 中国核动力研究设计院 | Large box device for running-state safety injection pump environment test and test method |
CN112820425A (en) * | 2021-02-08 | 2021-05-18 | 上海核工程研究设计院有限公司 | Systematic passive special safety system suitable for multipurpose reactor |
CN113035393A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
CN115359931A (en) * | 2022-07-01 | 2022-11-18 | 安徽中科超核科技有限公司 | A reactor safety protection system |
Citations (37)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4664877A (en) * | 1984-12-24 | 1987-05-12 | Westinghouse Electric Corp. | Passive depressurization system |
CN101856963A (en) * | 2009-04-02 | 2010-10-13 | 曼尼托沃克起重机有限责任公司 | Be used for providing the system of heat to construction equipment cab |
CN102637465A (en) * | 2012-05-02 | 2012-08-15 | 哈尔滨工程大学 | Passive containment cooling system |
CN102750993A (en) * | 2012-06-28 | 2012-10-24 | 中国核电工程有限公司 | Passive containment accident pressure-releasing system capable of containing discharged gas |
CN102867550A (en) * | 2012-08-20 | 2013-01-09 | 中国核电工程有限公司 | Passive heat removal device for dealing with station blackout accident |
CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
CN102903403A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Active and non-active combined core water injection heat lead-out device |
KR101242746B1 (en) * | 2011-12-14 | 2013-03-12 | 한국과학기술원 | Integrated passive safety system outside containment for nuclear power plants |
CN202855316U (en) * | 2012-09-11 | 2013-04-03 | 中科华核电技术研究院有限公司 | Containment cooling system for PWR (pressurized water reactor) nuclear power plant |
CN103206614A (en) * | 2013-04-01 | 2013-07-17 | 中山大学 | Early warning device and method for BLEVE accident monitoring of pressurized storage tanks |
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 |
US20140016734A1 (en) * | 2012-07-13 | 2014-01-16 | Korea Atomic Energy Research Institute | Passive safety system of integral reactor |
CN104091621A (en) * | 2014-07-24 | 2014-10-08 | 哈尔滨工程大学 | passive external cooling system |
WO2015050410A1 (en) * | 2013-10-04 | 2015-04-09 | 한국원자력연구원 | Passive safety equipment and nuclear power plant including same |
US20150117586A1 (en) * | 2013-10-28 | 2015-04-30 | BABCOCK & WILCOX mPOWER, INC | Alternative safety function system for nuclear reactor |
CN104681107A (en) * | 2015-02-12 | 2015-06-03 | 中国核电工程有限公司 | System and method for preventing inner shell failure and radioactive release of dual-layer containment |
CN104979022A (en) * | 2014-04-03 | 2015-10-14 | 国核(北京)科学技术研究院有限公司 | Non-active containment heat export system and pressurized water reactor |
CN105632570A (en) * | 2014-12-01 | 2016-06-01 | 上海核工程研究设计院 | Reactor shielding, coolant pressure relief and containment suppression compound device |
JP2016109503A (en) * | 2014-12-04 | 2016-06-20 | 日立Geニュークリア・エナジー株式会社 | Fuel coolant interaction influence mitigation system and nuclear power generation plant provided with same |
CN105719706A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Small reactor passive core cooling system |
CN205751539U (en) * | 2016-05-06 | 2016-11-30 | 上海核工程研究设计院 | A kind of special non-kinetic safety equipment of nuclear power station |
CN106251916A (en) * | 2016-08-31 | 2016-12-21 | 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 |
CN106297915A (en) * | 2015-05-12 | 2017-01-04 | 国核华清(北京)核电技术研发中心有限公司 | A kind of passive safety injection system for nuclear power station |
CN106531244A (en) * | 2016-11-28 | 2017-03-22 | 哈尔滨工程大学 | Passive containment vessel cooling system applicable to floating nuclear power plants |
CN107039096A (en) * | 2017-05-24 | 2017-08-11 | 长江勘测规划设计研究有限责任公司 | Filtering emission system under underground nuclear power station major accident |
US20170294240A1 (en) * | 2015-11-20 | 2017-10-12 | Elysium Industries Limited | Systems and methods for thermal interconnect |
CN107293338A (en) * | 2016-04-12 | 2017-10-24 | 国家电投集团科学技术研究院有限公司 | Nuclear reactor safety 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 |
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 |
CN108335764A (en) * | 2018-01-24 | 2018-07-27 | 中广核研究院有限公司 | A kind of small-sized heap spentnuclear fuel is cooling and purification system |
CN108470592A (en) * | 2018-02-28 | 2018-08-31 | 中国核电工程有限公司 | Expansion application method after a kind of nuclear power plant system accident |
US20190006052A1 (en) * | 2017-06-28 | 2019-01-03 | Ge-Hitachi Nuclear Energy Americas Llc | Isolation condenser systems for very simplified boiling water reactors |
CN109268686A (en) * | 2017-07-17 | 2019-01-25 | 国家电投集团科学技术研究院有限公司 | Constant-current stabilizer |
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 |
CN110246599A (en) * | 2019-05-08 | 2019-09-17 | 上海核工程研究设计院有限公司 | A kind of double heaps of compact reactor share weary pool device |
CN111128414A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Active and passive combined safety system and method for nuclear power plant |
CN111383782A (en) * | 2018-12-28 | 2020-07-07 | 国家电投集团科学技术研究院有限公司 | Passive safety system and pressurized water reactor with same |
-
2020
- 2020-09-15 CN CN202010965740.4A patent/CN112071454B/en active Active
Patent Citations (37)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4664877A (en) * | 1984-12-24 | 1987-05-12 | Westinghouse Electric Corp. | Passive depressurization system |
CN101856963A (en) * | 2009-04-02 | 2010-10-13 | 曼尼托沃克起重机有限责任公司 | Be used for providing the system of heat to construction equipment cab |
KR101242746B1 (en) * | 2011-12-14 | 2013-03-12 | 한국과학기술원 | Integrated passive safety system outside containment for nuclear power plants |
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 |
CN102637465A (en) * | 2012-05-02 | 2012-08-15 | 哈尔滨工程大学 | Passive containment cooling system |
CN102750993A (en) * | 2012-06-28 | 2012-10-24 | 中国核电工程有限公司 | Passive containment accident pressure-releasing system capable of containing discharged gas |
US20140016734A1 (en) * | 2012-07-13 | 2014-01-16 | Korea Atomic Energy Research Institute | Passive safety system of integral reactor |
CN102867550A (en) * | 2012-08-20 | 2013-01-09 | 中国核电工程有限公司 | Passive heat removal device for dealing with station blackout accident |
CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
CN202855316U (en) * | 2012-09-11 | 2013-04-03 | 中科华核电技术研究院有限公司 | Containment cooling system for PWR (pressurized water reactor) nuclear power plant |
CN102903403A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Active and non-active combined core water injection heat lead-out device |
CN103206614A (en) * | 2013-04-01 | 2013-07-17 | 中山大学 | Early warning device and method for BLEVE accident monitoring of pressurized storage tanks |
WO2015050410A1 (en) * | 2013-10-04 | 2015-04-09 | 한국원자력연구원 | Passive safety equipment and nuclear power plant including same |
US20150117586A1 (en) * | 2013-10-28 | 2015-04-30 | BABCOCK & WILCOX mPOWER, INC | Alternative safety function system for nuclear reactor |
CN104979022A (en) * | 2014-04-03 | 2015-10-14 | 国核(北京)科学技术研究院有限公司 | Non-active containment heat export system and pressurized water reactor |
CN104091621A (en) * | 2014-07-24 | 2014-10-08 | 哈尔滨工程大学 | passive external cooling system |
CN105719706A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Small reactor passive core cooling system |
CN105632570A (en) * | 2014-12-01 | 2016-06-01 | 上海核工程研究设计院 | Reactor shielding, coolant pressure relief and containment suppression compound device |
JP2016109503A (en) * | 2014-12-04 | 2016-06-20 | 日立Geニュークリア・エナジー株式会社 | Fuel coolant interaction influence mitigation system and nuclear power generation plant provided with same |
CN104681107A (en) * | 2015-02-12 | 2015-06-03 | 中国核电工程有限公司 | System and method for preventing inner shell failure and radioactive release of dual-layer containment |
CN106297915A (en) * | 2015-05-12 | 2017-01-04 | 国核华清(北京)核电技术研发中心有限公司 | A kind of passive safety injection system for nuclear power station |
US20170294240A1 (en) * | 2015-11-20 | 2017-10-12 | Elysium Industries Limited | Systems and methods for thermal interconnect |
CN107293338A (en) * | 2016-04-12 | 2017-10-24 | 国家电投集团科学技术研究院有限公司 | Nuclear reactor safety system |
CN205751539U (en) * | 2016-05-06 | 2016-11-30 | 上海核工程研究设计院 | A kind of special non-kinetic safety equipment of nuclear power station |
CN106251916A (en) * | 2016-08-31 | 2016-12-21 | 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 |
CN106531244A (en) * | 2016-11-28 | 2017-03-22 | 哈尔滨工程大学 | Passive containment vessel cooling system applicable to floating nuclear power plants |
CN107039096A (en) * | 2017-05-24 | 2017-08-11 | 长江勘测规划设计研究有限责任公司 | Filtering emission system under underground nuclear power station major accident |
US20190006052A1 (en) * | 2017-06-28 | 2019-01-03 | Ge-Hitachi Nuclear Energy Americas Llc | Isolation condenser systems for very simplified boiling water reactors |
CN109268686A (en) * | 2017-07-17 | 2019-01-25 | 国家电投集团科学技术研究院有限公司 | Constant-current stabilizer |
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 |
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 |
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 |
CN108335764A (en) * | 2018-01-24 | 2018-07-27 | 中广核研究院有限公司 | A kind of small-sized heap spentnuclear fuel is cooling and purification system |
CN108470592A (en) * | 2018-02-28 | 2018-08-31 | 中国核电工程有限公司 | Expansion application method after a kind of nuclear power plant system accident |
CN111383782A (en) * | 2018-12-28 | 2020-07-07 | 国家电投集团科学技术研究院有限公司 | Passive safety system and pressurized water reactor with same |
CN110246599A (en) * | 2019-05-08 | 2019-09-17 | 上海核工程研究设计院有限公司 | A kind of double heaps of compact reactor share weary pool device |
CN111128414A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Active and passive combined safety system and method for nuclear power plant |
Non-Patent Citations (3)
Title |
---|
俞冀阳等: "AC600非能动安全壳冷却系统长期效应分析", 《核动力工程》 * |
曹臻等: "超临界水冷堆典型非失水事故模拟", 《原子能科学技术》 * |
王开元等: "非能动余热排出换热器池沸腾换热性能研究", 《原子能科学技术》 * |
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CN112820425A (en) * | 2021-02-08 | 2021-05-18 | 上海核工程研究设计院有限公司 | Systematic passive special safety system suitable for multipurpose reactor |
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CN113035393B (en) * | 2021-03-05 | 2022-11-18 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
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