WO2021109136A1 - 核电厂非能动二次侧余热排出系统 - Google Patents
核电厂非能动二次侧余热排出系统 Download PDFInfo
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- WO2021109136A1 WO2021109136A1 PCT/CN2019/123733 CN2019123733W WO2021109136A1 WO 2021109136 A1 WO2021109136 A1 WO 2021109136A1 CN 2019123733 W CN2019123733 W CN 2019123733W WO 2021109136 A1 WO2021109136 A1 WO 2021109136A1
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- temperature zone
- waste heat
- removal system
- high temperature
- power plant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- 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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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the invention relates to the technical field of nuclear power, in particular to a passive secondary side waste heat discharge system of a nuclear power plant.
- a nuclear power plant accident refers to an abnormal state of the nuclear power plant due to individual human error or mechanical failure, which poses a risk of endangering the safety of the public and the environment.
- the physical parameters of the reactor and its related systems will undergo transient changes. These changes can be used to carry out related protection operations and use safety systems for accident mitigation.
- special safety facilities also known as safety systems
- safety systems need to be adopted for accident mitigation, so that the reactor can be gradually processed to a safe state.
- the nuclear power plant has set up a safety system to ensure that the reactor is shut down, the core waste heat is discharged, and the integrity of the containment is maintained in the event of a reactor accident, to avoid uncontrolled discharge of radioactive materials under any circumstances, to reduce equipment losses, and to protect the public and nuclear power
- the safety of the staff The safety of the staff.
- the emergency waste heat removal system is an important part of the safety system. Under accident conditions, it is used to discharge the core waste heat. It will discharge the waste heat to the final cold trap until the normal core waste heat removal system can intervene and combine Perform the function of exhausting the core waste heat.
- the emergency waste heat removal system includes a passive secondary side waste heat removal system and an active secondary side waste heat removal system.
- the inlet of the passive secondary side emergency waste heat exhaust system is connected to the steam side of the steam generator, and the outlet is connected to the water supply side of the steam generator, so the passive secondary side emergency waste heat exhaust system is connected with the steam generator to form a natural circulation loop (The steam generator is the heat trap of the loop, and the heat exchanger of the passive secondary side emergency waste heat removal system is the cold trap of the loop), which can remove the core waste heat of the primary loop of the reactor.
- the residual heat of the reactor core is exported to the cooling pool outside the containment, and the cooling water in the pool absorbs heat to heat up and evaporate.
- the main equipment of the passive secondary side waste heat removal system includes: the passive secondary side waste heat removal system heat exchanger, the cooling pool outside the containment, the water supply tank, other pipes and valves.
- the heat exchanger is located in the cooling water tank outside the containment vessel.
- the outside of the heat exchange tube is in contact with the water in the cooling water tank outside the containment vessel.
- the internal inlet of the heat exchange tube is connected to the main steam pipe of the reactor steam generator through the pipeline, and the outlet of the heat exchange tube is connected to the reactor.
- the cooling water tank outside the containment is a tank container, located at a higher elevation outside the containment, and contains cooling water.
- the water make-up tank is a tank container with cooling water in it, connected to the inlet and outlet pipes of the heat exchanger, and used to make up water for the passive secondary side waste heat discharge system.
- the existing cooling pool outside the containment is located outside the containment, at a higher vertical position relative to the steam generator. There is no partition in the cooling pool outside the containment. Once the heat exchange is performed, all the cooling water is heated and raised, and all the inner walls of the cooling pool outside the containment are steel cladding. This results in more steel cladding and higher economic costs. And the construction period is longer.
- the technical problem to be solved by the present invention is to provide a passive secondary side waste heat removal system of a nuclear power plant that can reduce the cost and improve the economy.
- the technical solution adopted by the present invention to solve its technical problems is to provide a passive secondary side waste heat discharge system of a nuclear power plant, which includes a cooling water pool, a heat exchanger arranged in the cooling water pool, and an inlet of the heat exchanger Connected to the steam side of the steam generator, and the outlet connected to the water supply side of the steam generator; further comprising a partition arranged in the cooling pool;
- the partition separates the accommodating space of the cooling pool into a high temperature zone and a low temperature zone, and the heat exchanger is located in the high temperature zone; the partition is provided with a plurality of flowing water connecting the high temperature zone and the low temperature zone hole.
- the inner wall surface of the high temperature zone is a steel cladding surface.
- the pore diameter of the water flow hole is 1 cm-10 cm.
- the hole diameter of the water flow hole is 10 cm-50 cm.
- a check valve is provided in the water flow hole to prevent water in the high temperature zone from flowing to the low temperature zone.
- the passive secondary side waste heat removal system of the nuclear power plant further includes a water pipe connected to the water flow hole or fitted in the water flow hole; the water pipe is provided with a water pipe that prevents the water in the high temperature area from flowing to the low temperature area.
- Check valve is provided to the water flow hole or fitted in the water flow hole; the water pipe is provided with a water pipe that prevents the water in the high temperature area from flowing to the low temperature area.
- the passive secondary side waste heat removal system of the nuclear power plant further includes a one-way orifice door covering the water flow hole in the high temperature zone.
- the temperature difference between the high temperature zone and the low temperature zone is 40°C-100°C.
- the temperature difference ⁇ T between the high temperature zone and the low temperature zone depends on the following factors: the volume ratio K of the high temperature zone and the low temperature zone, and the ratio of the total cross-sectional area of the water flow hole to the total volume of the cooling pool M.
- the beneficial effect of the present invention is that the cooling pool is divided into a high temperature zone and a low temperature zone by arranging partitions, and the heat exchanger is placed in the high temperature zone, so that there is a temperature difference between the high temperature zone and the low temperature zone, so that only the high temperature zone is located in the cooling pool.
- the steel cladding needs to be installed, and the low-temperature zone is not needed, which can avoid the installation of a larger area of steel cladding, thereby reducing the construction period, lowering the cost, and improving the economy.
- FIG. 1 is a schematic cross-sectional structure diagram of a passive secondary side waste heat removal system of a nuclear power plant according to a first embodiment of the present invention
- FIG. 2 is a schematic cross-sectional structure diagram of a passive secondary side waste heat removal system of a nuclear power plant according to a second embodiment of the present invention
- FIG. 3 is a schematic cross-sectional structure diagram of a passive secondary side waste heat removal system of a nuclear power plant according to a third embodiment of the present invention.
- the passive secondary side waste heat removal system of a nuclear power plant includes a cooling pool 10, a heat exchanger 20 and a partition 30 arranged in the cooling pool 10.
- the cooling pool 10 is located outside the containment vessel, and the location of the cooling pool 10 is higher than that of the steam generator in the vertical direction.
- the inlet of the heat exchanger 20 is connected to the steam side of the steam generator, and the outlet is connected to the water supply side of the steam generator.
- the partition 30 separates the accommodating space of the cooling pool 10 into a high temperature zone 101 and a low temperature zone 102 in the cooling pool 10, and the heat exchanger 20 is located in the high temperature zone 101.
- the partition 30 is provided with a number of water holes 31 connecting the high temperature zone 101 and the low temperature zone 102.
- the function of the water flow hole 31 is to provide small communication between the high temperature zone 101 and the low temperature zone 102, but avoid larger communication, so that the cooling water in the low temperature zone 102 can maintain a lower temperature than the cooling water in the high temperature zone 101.
- the lower part of the accommodating space of the cooling pool 10 is cooling water, and the upper part is air.
- the top of the cooling pool 10 is provided with a cover plate, and the cover plate does not need to be sealed on the cooling pool 10.
- the high temperature zone 101 bears a higher temperature than the low temperature zone 102. Therefore, the inner wall surface of the high temperature zone 101 is provided with steel cladding.
- the cooling pool 10 is usually a concrete structure made of concrete materials. The function of the steel cladding is to block the concrete structure around the cooling pool 10 and the high-temperature fluid in the cooling pool 10, so as to prevent the concrete structure from directly bearing higher temperatures, thereby avoiding coagulation structural factors. High temperature exceeds the stress limit.
- the thickness and specific material of the steel cladding can be selected according to actual needs, or can be achieved by using the existing technology.
- the partition 30 can be formed by stacking concrete materials, that is, a concrete partition wall is formed, and the cost is low.
- the surface of the partition 30 facing the high-temperature zone 101 also serves as the inner wall surface of the high-temperature zone 101, so a steel cladding is also provided.
- the inner wall surface of the low temperature zone 102 (including the surface of the partition 30 facing the low temperature zone 102) does not need to be provided with a steel cladding.
- the water flow hole 31 provided on the partition 30 is a hole with a smaller diameter, such as a hole diameter of 1 cm-10 cm. According to the smaller the hole, the worse the connectivity, the smaller the diameter of the water hole 31 is, the connectivity between the high temperature zone 101 and the low temperature zone 102 can be reduced, thereby reducing the flow of cooling water between the two, thereby increasing the high temperature The temperature difference between zone 101 and low temperature zone 102.
- the inlet of the heat exchanger 20 is connected to the steam side of the steam generator through a de-steaming pipe 41, and the outlet of the heat exchanger 20 is connected to the water supply side of the steam generator through a return water pipe 42.
- the steam discharged from the steam generator enters the heat exchanger 20 through the degassing pipe 41. After heat exchange with the cooling water in the high temperature zone 101 in the heat exchanger 20, the condensed back to the liquid state flows back to the steam generator through the return water pipe 42 .
- the water flow holes 31 can be divided into two groups, one group is located at the upper end of the partition 30 and the other group is located at the lower end of the partition 30.
- the cooling water in the high temperature zone 101 increases in temperature due to heat exchange, and can flow from a set of water holes located at the upper end of the partition 30 to the low temperature zone 102; the cooling water in the low temperature zone 102 can flow from a set of water holes located at the lower end of the partition 30
- the water holes flow to the high temperature zone 101, and the total amount of cooling water flowing from the low temperature zone 102 to the high temperature zone 101 is greater than the heated cooling water flowing from the high temperature zone 101 to the low temperature zone 102.
- the overall cooling water in the low temperature zone 102 always maintains a lower temperature , Forming a temperature difference with the high temperature zone 101.
- the passive secondary side waste heat removal system of a nuclear power plant includes a cooling pool 10, a heat exchanger 20 and a partition 30 arranged in the cooling pool 10.
- the cooling pool 10 is located outside the containment vessel, and the location of the cooling pool 10 is higher than that of the steam generator in the vertical direction.
- the inlet of the heat exchanger 20 is connected to the steam side of the steam generator, and the outlet is connected to the water supply side of the steam generator.
- the partition 30 separates the accommodating space of the cooling pool 10 into a high temperature zone 101 and a low temperature zone 102 in the cooling pool 10, and the heat exchanger 20 is located in the high temperature zone 101.
- the partition 30 is provided with a number of water holes 31 connecting the high temperature zone 101 and the low temperature zone 102.
- the function of the water flow hole 31 is to provide small communication between the high temperature zone 101 and the low temperature zone 102, but avoid larger communication, so that the cooling water in the low temperature zone 102 can maintain a lower temperature than the cooling water in the high temperature zone 101.
- the steel cladding in the high-temperature zone 101 of the cooling water pool 10 and the arrangement of the partition 30 can be referred to the above-mentioned first embodiment, which will not be repeated here.
- the water flow hole 31 is a hole with a larger diameter, such as a hole diameter of 10 cm-50 cm, and the connectivity is higher than that of the water flow hole 31 in the first embodiment.
- a check valve 32 is provided in the water flow hole 31 to prevent the water in the high temperature zone 101 from flowing to the low temperature zone 102.
- the setting of the check valve 32 makes the cooling water flow only from the low temperature area 102 to the high temperature area 101.
- the check valve 32 has a set opening pressure difference, that is, only when the pressure difference between the two sides of the check valve 32 (the pressure in the low temperature zone 102 minus the pressure in the high temperature zone 101) reaches the set value, the valve will open, so the actual operation At this time, the liquid level of the cooling water in the high temperature zone 101 and the low temperature zone 102 will maintain a certain level difference, so as to form the pressure difference required for valve opening through the gravity pressure difference.
- the passive secondary side waste heat removal system of the nuclear power plant of this embodiment may further include a water pipe 33 connected to the water flow hole 31 or fitted in the water flow hole 31.
- the check valve 32 may be provided in the water pipe 33.
- the inlet of the heat exchanger 20 is connected to the steam side of the steam generator through a de-steaming pipe, and the outlet of the heat exchanger 20 is connected to the water supply side of the steam generator through a return water pipe.
- the steam discharged from the steam generator enters the heat exchanger 20 through the degassing pipe, exchanges heat with the cooling water in the high temperature zone 101 in the heat exchanger 20, and then condenses, and flows back to the steam generator through the return water pipe.
- the temperature of the cooling water in the high temperature zone 101 increases due to heat exchange, and the liquid level decreases after partial vaporization, forming a pressure difference with the low temperature zone 102 (the liquid level is higher than the high temperature zone 101), so that the cooling water in the low temperature zone 102 can pass through
- the water flow hole 31 is supplemented to the high temperature zone 101.
- the low temperature zone 102 always maintains a relatively low temperature, forming a temperature difference with the high temperature zone 101.
- the passive secondary side waste heat removal system of a nuclear power plant includes a cooling pool 10, a heat exchanger 20 and a partition 30 arranged in the cooling pool 10.
- the cooling pool 10 is located outside the containment, and the location of the cooling pool 10 is higher than that of the steam generator in the vertical direction.
- the inlet of the heat exchanger 20 is connected to the steam side of the steam generator, and the outlet is connected to the water supply side of the steam generator.
- the partition 30 separates the accommodating space of the cooling pool 10 into a high temperature zone 101 and a low temperature zone 102 in the cooling pool 10, and the heat exchanger 20 is located in the high temperature zone 101.
- the partition 30 is provided with a plurality of water holes 31 connecting the high temperature zone 101 and the low temperature zone 102.
- the function of the water flow hole 31 is to provide relatively small communication between the high temperature zone 101 and the low temperature zone 102, but avoid greater communication, so that the cooling water in the low temperature zone 102 maintains a lower temperature than the cooling water in the high temperature zone 101.
- the steel cladding in the high-temperature zone 101 of the cooling water pool 10 and the arrangement of the partition 30 can be referred to the above-mentioned first embodiment, which will not be repeated here.
- the water flow hole 31 is a hole with a larger diameter, such as a hole diameter of 10 cm-50 cm, and the connectivity is higher than that of the water flow hole 31 in the first embodiment.
- the passive secondary side waste heat removal system of the nuclear power plant of this embodiment further includes a one-way orifice door 34 that can be opened and closed to cover the water flow hole 31.
- the one-way orifice door 34 is located in the high temperature zone 101, that is, covers the opening of the water flow hole 31 in the high temperature zone 101.
- the one-way orifice door 34 can only be opened to the side of the high temperature zone, and a certain pressure is required to open, so that the one-way orifice door 34 can be opened when the low temperature zone 102 and the high temperature zone 101 have a certain pressure difference, and the coolant in the low temperature zone 102 can pass through Flow to the high temperature zone 101.
- the low temperature zone 102 always maintains a relatively low temperature, forming a temperature difference with the high temperature zone 101.
- the passive secondary side waste heat removal system of the nuclear power plant of the present invention also includes a make-up tank (not shown) connected between the degassing pipe 41 and the return water pipe 42 to play the role of water replenishment.
- the cooling pool 10 is divided into a high temperature zone 101 and a low temperature zone 102, so that the high temperature zone 101 and the low temperature zone 102 A certain appropriate temperature difference ( ⁇ T) is maintained, and no steel cladding is required to realize the low temperature zone 102.
- ⁇ T temperature difference
- the temperature difference between the high temperature zone 101 and the low temperature zone 102 is preferably 40°C-100°C.
- the high temperature zone 101 Since the high temperature zone 101 is in an atmospheric environment, it will be heated to the saturation temperature of atmospheric pressure after the system is started; the lower the temperature of the low temperature zone 102, the lower the requirement for the inner wall surface to withstand high temperature, which is more advantageous for its materials and construction.
- the greater the temperature difference the smaller the ratio of the total cross-sectional area of the water flow hole 31 to the volume of the cooling water pool 10 is required, which will cause the flowability of the high temperature region 101 to the low temperature region 102 to deteriorate.
- the temperature difference ⁇ T between the high temperature zone 101 and the low temperature zone 102 depends on the following factors: the volume ratio K of the high temperature zone 101 and the low temperature zone 102, the total cross-sectional area of the water hole 31 to the total volume ratio M of the cooling pool 10, and the cooling pool 10
- the temperature difference ⁇ T is the target parameter
- the ratio V/W is a determined value that can be obtained according to the total volume of the cooling pool 10 and the rated power of the selected heat exchanger 20, according to ⁇ T and V/W Simulate in related software to obtain K and M.
- the high temperature zone 101 and the low temperature zone 102 corresponding to the volume ratio are provided with the corresponding number and diameter of the water flow holes 31 according to the total cross-sectional area of the water flow holes 31 as required.
Abstract
一种核电厂非能动二次侧余热排出系统，包括冷却水池（10）、设置在冷却水池（10）内的换热器（20）；换热器（20）的入口连接蒸汽发生器的蒸汽侧，出口连接蒸汽发生器的给水侧；还包括设置在冷却水池（10）内的分隔件（30）；分隔件（30）将冷却水池（10）的容纳空间分隔为高温区（101）和低温区（102），换热器（20）位于高温区（101）内；分隔件（30）上设有若干连通高温区（101）和低温区（102）的流水孔（31）。通过设置分隔件（30），该余热排出系统将冷却水池（10）分隔为高温区（101）和低温区（102），换热器（20）置于高温区（101）内，使得高温区（101）和低温区（102）具有温度差，进而使得在冷却水池（10）内仅高温区（101）需要设置钢覆面，低温区（102）不需要，可避免设置较大面积的钢覆面，从而减少工期、降低造价，提升经济性。
Description
本发明涉及核电技术领域，尤其涉及一种核电厂非能动二次侧余热排出系统。
核电厂的事故，是指因个别的人因差错或机械失效，导致核电厂状态异常，出现危及公众和环境安全的风险。发生核电厂事故以后，反应堆及其相关系统的物理参数将发生瞬态变化，可依据这些变化来进行相关保护操作，动用安全系统进行事故缓解。对于大部分的核电厂事故，需要采用专设安全设施（又称安全系统）进行事故缓解，以将反应堆逐渐处理至安全的状态。
核电厂设置了安全系统，是为了在反应堆事故情况下确保反应堆停堆、排出堆芯余热、保持安全壳的完整性，避免在任何情况下放射性物质的失控排放，减少设备损失，保护公众和核电工作人员的安全。其中，应急余热排出系统，是安全系统的重要组成部分，在事故工况下，用于排出堆芯余热，它将余热排出至最终的冷阱，直到正常的堆芯余热排出系统可以介入、并执行排出堆芯余热的功能。应急余热排出系统包括有非能动二次侧余热排出系统和能动二次侧余热排出系统。
非能动二次侧应急余热排出系统的入口连接于蒸汽发生器蒸汽侧，出口连接于蒸汽发生器的给水侧，因此非能动二次侧应急余热排出系统与蒸汽发生器衔接配合，形成自然循环回路（蒸汽发生器为该回路的热阱，非能动二次侧应急余热排出系统换热器为该回路的冷阱），可以移出反应堆一回路的堆芯余热。将堆芯余热导出至安全壳外冷却水池，水池内冷却水吸热升温并蒸发。
非能动二次侧余热排出系统的主要设备包括：非能动二次侧余热排出系统换热器、安全壳外冷却水池、补水箱、其他管道与阀门。换热器位于安全壳外冷却水箱中，换热管外部接触安全壳外冷却水箱的水，换热管内部的进口通过管道连接于反应堆蒸汽发生器主蒸汽管道，换热管的出口连接于反应堆蒸汽发生器的辅助给水管道或主给水管道。安全壳外冷却水箱为罐式容器，位于安全壳外标高较高的位置，内装冷却水。补水箱为罐式容器，其中装有冷却水，连接于换热器的进出口管道，用于给非能动二次侧余热排出系统补水。
现有安全壳外冷却水池，位于安全壳外，相对蒸汽发生器垂直较高的位置。安全壳外冷却水池中未设置分区，一旦进行热交换后所有冷却水都被加热升温，并且安全壳外冷却水池的所有内壁面均为钢覆面，这样造成钢覆面较多、经济代价较大，且施工周期较长。
本发明要解决的技术问题在于，提供一种能够降低造价、提升经济性的核电厂非能动二次侧余热排出系统。
本发明解决其技术问题所采用的技术方案是：提供一种核电厂非能动二次侧余热排出系统，包括冷却水池、设置在所述冷却水池内的换热器；所述换热器的入口连接蒸汽发生器的蒸汽侧，出口连接蒸汽发生器的给水侧；还包括设置在所述冷却水池内的分隔件；
所述分隔件将所述冷却水池的容纳空间分隔为高温区和低温区，所述换热器位于所述高温区内；所述分隔件上设有若干连通所述高温区和低温区的流水孔。
优选地，所述高温区的内壁面为钢覆面。
优选地，所述流水孔的孔径为1cm-10cm。
优选地，所述流水孔的孔径为10cm-50cm。
优选地，所述流水孔内设有防止高温区的水流向低温区的逆止阀。
优选地，所述核电厂非能动二次侧余热排出系统还包括连接所述流水孔或配合在所述流水孔中的流水管；所述流水管中设有防止高温区的水流向低温区的逆止阀。
优选地，所述核电厂非能动二次侧余热排出系统还包括于所述高温区中覆盖在所述流水孔上的单向孔门。
优选地，所述高温区和低温区的温度差值为40℃-100℃。
优选地，所述高温区和低温区的温度差值ΔT取决于如下因素：所述高温区和低温区的体积比例K、所述流水孔的总横截面面积相对所述冷却水池的总体积比值M、所述冷却水池总体积相对所述换热器额定功率的比例V/W，各因素的关系为ΔT=( K, M,( V/W))。
优选地，通过三维计算流体学模拟软件或者系统热工水力软件开展模拟仿真，以V/W为确定性的输入、以ΔT为40℃-100℃为目标，根据各因素的关系ΔT=( K, M,( V/W))确定K和M。
本发明的有益效果：通过设置分隔件，将冷却水池分隔为高温区和低温区，换热器置于高温区内，使得高温区和低温区具有温度差，进而使得在冷却水池内仅高温区需要设置钢覆面，低温区不需要，可避免设置较大面积的钢覆面，从而减少工期、降低造价，提升经济性。
下面将结合附图及实施例对本发明作进一步说明，附图中：
图1是本发明第一实施例的核电厂非能动二次侧余热排出系统的剖面结构示意图；
图2是本发明第二实施例的核电厂非能动二次侧余热排出系统的剖面结构示意图；
图3是本发明第三实施例的核电厂非能动二次侧余热排出系统的剖面结构示意图。
为了对本发明的技术特征、目的和效果有更加清楚的理解，现对照附图详细说明本发明的具体实施方式。
如图1所示，本发明第一实施例的核电厂非能动二次侧余热排出系统，包括冷却水池10、设置在冷却水池10内的换热器20和分隔件30。
在核电厂中，冷却水池10位于安全壳外，冷却水池10所处位置在垂直方向上高于蒸汽发生器所处位置。换热器20的入口连接蒸汽发生器的蒸汽侧，出口连接蒸汽发生器的给水侧。分隔件30在冷却水池10内将冷却水池10的容纳空间分隔为高温区101和低温区102，换热器20位于高温区101内。分隔件30上设有若干连通高温区101和低温区102的流水孔31。流水孔31的作用在于为高温区101和低温区102提供较小的连通，但是又避免较大的连通，从而使低温区102内冷却水相对高温区101内冷却水保持较低的温度。
其中，冷却水池10池的容纳空间下部为冷却水，上部为空气。冷却水池10顶部设置盖板，盖板不需密封在冷却水池10上。
在冷却水池10内，高温区101相对于低温区102承受较高的温度，因此，高温区101的内壁面均设置钢覆面。冷却水池10通常是采用混凝土材料制成的混凝土结构，钢覆面的作用在于阻隔冷却水池10四周混凝土结构和冷却水池10内的高温流体，避免混凝土结构直接承受较高温度，从而避免混凝结构因高温而超过应力极限。
钢覆面的厚度和具体材料可以根据实际需要进行选择，也可以采用现有技术的设置实现。
分隔件30可以采用混凝土材料堆砌形成，即形成混凝土分隔墙，造价低。该分隔件30朝向高温区101的表面也作为高温区101的内壁面，因此也设置钢覆面。低温区102的内壁面（包括分隔件30朝向低温区102的表面）不需设置钢覆面。
本实施例中，设置在分隔件30上的流水孔31为直径较小的孔，如孔径为1cm-10cm。根据孔越小连通性越差，将流水孔31孔径较小设置，可以降低高温区101和低温区102之间的连通性，从而降低两者之间冷却水的流通量，进而可以增大高温区101和低温区102之间的温差。
在冷却水池10的高温区101，换热器20的入口通过去汽管道41连接蒸汽发生器的蒸汽侧，换热器20的出口通过回水管道42连接蒸汽发生器的给水侧。蒸汽发生器排出的蒸汽通过去汽管道41进入换热器20内，在换热器20内与高温区101内的冷却水进行热交换后，冷凝回液态通过回水管道42流回蒸汽发生器。
该实施例中，流水孔31可分成两组，一组位于分隔件30的上端，另一组位于分隔件30的下端。高温区101内的冷却水由于经过热交换而温度升高，可以从位于分隔件30的上端的一组流水孔流向低温区102；低温区102的冷却水可从位于分隔件30下端的一组流水孔流向高温区101，且从低温区102流向高温区101的冷却水总量大于从高温区101流向低温区102的加热后的冷却水，整体低温区102的冷却水始终保持较低的温度，与高温区101形成温度差。
如图2所示，本发明第二实施例的核电厂非能动二次侧余热排出系统，包括冷却水池10、设置在冷却水池10内的换热器20和分隔件30。
在核电厂中，冷却水池10位于安全壳外，冷却水池10所处位置在垂直方向上高于蒸汽发生器所处位置。换热器20的入口连接蒸汽发生器的蒸汽侧，出口连接蒸汽发生器的给水侧。分隔件30在冷却水池10内将冷却水池10的容纳空间分隔为高温区101和低温区102，换热器20位于高温区101内。分隔件30上设有若干连通高温区101和低温区102的流水孔31。流水孔31的作用在于为高温区101和低温区102提供较小的连通，但是又避免较大的连通，从而使低温区102内冷却水相对高温区101内冷却水保持较低的温度。
冷却水池10的高温区101内钢覆面以及分隔件30的设置等均可参考上述第一实施例，在此不再赘述。
在本实施例中，流水孔31为直径较大的孔，如孔径为10cm-50cm，连通性相较于第一实施例中的流水孔31的连通性高。
进一步地，本实施例中，流水孔31内设有防止高温区101的水流向低温区102的逆止阀32。逆止阀32的设置，使得冷却水的流动方向仅为低温区102往高温区101。逆止阀32具有设定的开启压差，即只有当逆止阀32的阀门两侧压差（低温区102压力减去高温区101压力）达到设定值，阀门才会开启，因此实际运行时，高温区101和低温区102的冷却水液面会保持一定的液位差，以通过重力压差形成阀门开启所需的压差。
进一步地，本实施例的核电厂非能动二次侧余热排出系统还可包括连接流水孔31或配合在流水孔31中的流水管33。对于增设的流水管33，逆止阀32可设置在流水管33内。
在冷却水池10的高温区101，换热器20的入口通过去汽管道连接蒸汽发生器的蒸汽侧，换热器20的出口通过回水管道连接蒸汽发生器的给水侧。蒸汽发生器排出的蒸汽通过去汽管道进入换热器20内，在换热器20内与高温区101内的冷却水进行热交换后冷凝，通过回水管道流回蒸汽发生器。
高温区101内的冷却水由于经过热交换而温度升高，部分汽化后液位降低，与低温区102（液面高于高温区101）形成有压力差，从而低温区102的冷却水可通过流水孔31补充至高温区101。低温区102始终保持较低的温度，与高温区101形成温度差。
如图3所示，本发明第三实施例的核电厂非能动二次侧余热排出系统，包括冷却水池10、设置在冷却水池10内的换热器20和分隔件30。
在核电厂中，冷却水池10位于安全壳外，冷却水池10所处位置在垂直方向上高于蒸汽发生器所处位置。换热器20的入口连接蒸汽发生器的蒸汽侧，出口连接蒸汽发生器的给水侧。分隔件30在冷却水池10内将冷却水池10的容纳空间分隔为高温区101和低温区102，换热器20位于高温区101内。分隔件30上设有若干连通高温区101和低温区102的流水孔31。流水孔31的作用在于为高温区101和低温区102提供较小的连通，但是又避免较大的连通，从而使低温区102内冷却水相对高温区101内冷却水保持较低的温度。
冷却水池10的高温区101内钢覆面以及分隔件30的设置等均可参考上述第一实施例，在此不再赘述。
在本实施例中，流水孔31为直径较大的孔，如孔径为10cm-50cm，连通性相较于第一实施例中的流水孔31的连通性高。
对应流水孔31，本实施例的核电厂非能动二次侧余热排出系统还包括可开合覆盖在水流孔31上的单向孔门34。单向孔门34位于高温区101中，即覆盖在流水孔31位于高温区101的开口上。单向孔门34只能往高温区侧开启，且开启需要一定的压力推动，从而使得低温区102与高温区101具有一定压力差时才能打开单向孔门34，低温区102的冷却剂通过流到高温区101。低温区102始终保持较低的温度，与高温区101形成温度差。
可以理解地，本发明的核电厂非能动二次侧余热排出系统还包括连接在去汽管道41和回水管道42之间的补水箱（未图示），起到补水的作用。
另外，如图1-3所示，本发明的核电厂非能动二次侧余热排出系统中，通过将冷却水池10内分隔为高温区101和低温区102，在于使高温区101和低温区102保持一定合适的温度差（ΔT），实现低温区102无需设置钢覆面。综合考虑冷却水池10的混凝土承温特性和流水孔31的流通性等，高温区101和低温区102的温度差优选为40℃-100℃。
高温区101由于处于大气环境中，系统启动后将被加热至大气压的饱和温度；低温区102温度越低，对于内壁面承受高温的要求越低，这样对其材料和建造施工越有利。但是，温差越大，需要更小的流水孔31总横截面积相对冷却水池10体积比值，会导致高温区101向低温区102的流通性变差。
高温区101和低温区102的温度差值ΔT取决于如下因素：高温区101和低温区102的体积比例K、流水孔31的总横截面面积相对冷却水池10的总体积比值M、冷却水池10总体积相对换热器额定功率的比例V/W，即存在如下关系：ΔT=( K, M,( V/W))。在上述的各参数中，温度差值ΔT是目标参数，比例V/W是可以根据冷却水池10总体积和所选用的换热器20额定功率获得的已确定的数值，根据ΔT和V/W在相关软件模拟来获得K和M。
具体地，本发明可通过三维计算流体学模拟软件（CFD）或者系统热工水力软件（RELAP或Gothic）开展模拟仿真，以ΔT为40℃-100℃为目标，根据ΔT=( K, M,( V/W))确定K和M（多种组合），从而可以得到高温区101和低温区102所要设置的体积比以及流水孔31所需的总横截面面积，进而可以在实际中设定对应体积比的高温区101和低温区102，按照流水孔31的总横截面面积根据需要设置对应数量、孔径的流水孔31。
以上所述仅为本发明的实施例，并非因此限制本发明的专利范围，凡是利用本发明说明书及附图内容所作的等效结构或等效流程变换，或直接或间接运用在其他相关的技术领域，均同理包括在本发明的专利保护范围内。
Claims (10)
- 一种核电厂非能动二次侧余热排出系统，包括冷却水池、设置在所述冷却水池内的换热器；所述换热器的入口连接蒸汽发生器的蒸汽侧，出口连接蒸汽发生器的给水侧；其特征在于，还包括设置在所述冷却水池内的分隔件；所述分隔件将所述冷却水池的容纳空间分隔为高温区和低温区，所述换热器位于所述高温区内；所述分隔件上设有若干连通所述高温区和低温区的流水孔。
- 根据权利要求1所述的核电厂非能动二次侧余热排出系统，其特征在于，所述高温区的内壁面为钢覆面。
- 根据权利要求1所述的核电厂非能动二次侧余热排出系统，其特征在于，所述流水孔的孔径为1cm-10cm。
- 根据权利要求1所述的核电厂非能动二次侧余热排出系统，其特征在于，所述流水孔的孔径为10cm-50cm。
- 根据权利要求4所述的核电厂非能动二次侧余热排出系统，其特征在于，所述流水孔内设有防止高温区的水流向低温区的逆止阀。
- 根据权利要求4所述的核电厂非能动二次侧余热排出系统，其特征在于，所述核电厂非能动二次侧余热排出系统还包括连接所述流水孔或配合在所述流水孔中的流水管；所述流水管中设有防止高温区的水流向低温区的逆止阀。
- 根据权利要求4所述的核电厂非能动二次侧余热排出系统，其特征在于，所述核电厂非能动二次侧余热排出系统还包括于所述高温区中覆盖在所述流水孔上的单向孔门。
- 根据权利要求1-7任一项所述的核电厂非能动二次侧余热排出系统，其特征在于，所述高温区和低温区的温度差值为40℃-100℃。
- 根据权利要求8所述的核电厂非能动二次侧余热排出系统，其特征在于，所述高温区和低温区的温度差值ΔT取决于如下因素：所述高温区和低温区的体积比例K、所述流水孔的总横截面面积相对所述冷却水池的总体积比值M、所述冷却水池总体积相对所述换热器额定功率的比例V/W，各因素的关系为ΔT=( K, M,( V/W))。
- 根据权利要求9所述的核电厂非能动二次侧余热排出系统，其特征在于，通过三维计算流体学模拟软件或者系统热工水力软件开展模拟仿真，以V/W为确定性的输入、以ΔT为40℃-100℃为目标，根据各因素的关系ΔT=( K, M,( V/W))确定K和M。
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