CN106816186A - A kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe - Google Patents
A kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe Download PDFInfo
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- 238000007599 discharging Methods 0.000 title 1
- 239000002826 coolant Substances 0.000 claims abstract description 70
- 239000002918 waste heat Substances 0.000 claims abstract description 47
- 238000001704 evaporation Methods 0.000 claims abstract description 14
- 230000000630 rising effect Effects 0.000 claims abstract description 10
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 10
- 238000002955 isolation Methods 0.000 claims abstract description 9
- 238000009833 condensation Methods 0.000 claims abstract description 6
- 230000005494 condensation Effects 0.000 claims abstract description 6
- 239000012530 fluid Substances 0.000 claims description 10
- 230000001174 ascending effect Effects 0.000 claims description 7
- 239000003795 chemical substances by application Substances 0.000 claims 1
- 238000001816 cooling Methods 0.000 claims 1
- 239000013535 sea water Substances 0.000 description 14
- 230000008020 evaporation Effects 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000006641 stabilisation Effects 0.000 description 1
- 238000011105 stabilization Methods 0.000 description 1
- 230000005514 two-phase flow Effects 0.000 description 1
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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
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Abstract
本发明提供一种基于分离式热管的一体化压水堆非能动余热排出系统,包括主冷却剂系统、热交换器、热管冷凝段,主冷却剂系统的上充通道通过冷却剂下降管与热交换器的壳侧出口连接,主冷却剂系统的下泄通道通过冷却剂上升管与热交换器的壳侧入口连接,热交换器的蒸发段管束入口联箱通过下降管与热管冷凝段的出口联箱连接,热交换器的蒸发段管束出口联箱通过上升管与热管冷凝段的入口联箱连接,热管冷凝段上端设置有释放阀,冷却剂上升管上设置有常开隔离阀,冷却剂下降管上设置有非能动隔离阀。本发明在提高系统固有安全性的同时,保证对反应堆冷却剂的隔离、满足较长距离热量传递需求并简化系统设计。
The invention provides an integrated pressurized water reactor passive waste heat removal system based on separate heat pipes, which includes a main coolant system, a heat exchanger, and a heat pipe condensation section. The outlet of the shell side of the exchanger is connected, the drain channel of the main coolant system is connected with the shell side inlet of the heat exchanger through the coolant riser pipe, and the inlet header of the tube bundle of the evaporating section of the heat exchanger is connected with the outlet of the condensing section of the heat pipe through the downcomer. The outlet header of the evaporating section of the heat exchanger is connected to the inlet header of the condensing section of the heat pipe through the rising pipe. A passive isolation valve is provided on the pipe. While improving the inherent safety of the system, the invention ensures the isolation of the reactor coolant, satisfies the requirement of long-distance heat transfer and simplifies the system design.
Description
技术领域technical field
本发明涉及一种基于分离式热管的一体化压水堆非能动余热排出系统,属于核电站安全技术领域。The invention relates to an integrated pressurized water reactor passive waste heat discharge system based on separate heat pipes, belonging to the technical field of nuclear power plant safety.
背景技术Background technique
由于衰变热等大量余热的产生,在反应堆停堆后,需要设置专门的余热排出系统来保证堆芯余热的排出,否则将导致压力容器内压力和温度的持续升高,对压力容器的完整性造成威胁。现有核电站设置的余热排出系统绝大多数为能动设备,在运行时需要外部设备提供动力,这就使得余排设备存在当外部动力源丧失时丧失功能的风险,对反应堆安全造成威胁。Due to the generation of a large amount of waste heat such as decay heat, after the reactor is shut down, it is necessary to set up a special waste heat removal system to ensure the discharge of the waste heat from the core, otherwise it will cause the pressure and temperature in the pressure vessel to continue to rise, which will damage the integrity of the pressure vessel. create a threat. Most of the waste heat removal systems installed in existing nuclear power plants are active equipment, which require external equipment to provide power during operation. This makes the waste heat removal equipment risk losing function when the external power source is lost, posing a threat to the safety of the reactor.
随着核电工业的发展,一体化反应堆因其体积小,安全性高,各个国家都对其在特殊环境下如船舶动力、海洋平台、岛屿发电等的应用进行了探索和验证。一体化反应堆的应用环境往往远离陆地,装置可布置的空间受到限制,这就要求专设安全系统的设计在保证反应堆安全性的同时提高系统的固有安全性、较小的设备尺寸并简化结构设计。现有的非能动余热排出系统设计主要针对陆上商用核电站,辅助设施多,结构尺寸大,系统设计较为复杂,不适用于一体化反应堆的特殊环境。此外现有的非能动余热排出系统的循环工质在换热过程中大多保持单相,换热效率较低,需要较大的高度差获得稳定的自然循环流量,使得设备尺寸过大。With the development of the nuclear power industry, various countries have explored and verified the application of integrated reactors in special environments such as ship power, offshore platforms, and island power generation due to their small size and high safety. The application environment of integrated reactors is often far away from the land, and the space where the devices can be arranged is limited, which requires the design of an ad hoc safety system to ensure the safety of the reactor while improving the inherent safety of the system, reducing the size of the equipment and simplifying the structural design . The existing passive waste heat removal system is mainly designed for land-based commercial nuclear power plants, with many auxiliary facilities, large structure size, and complicated system design, which is not suitable for the special environment of integrated reactors. In addition, the circulating working medium of the existing passive waste heat removal system mostly maintains a single phase during the heat exchange process, the heat exchange efficiency is low, and a large height difference is required to obtain a stable natural circulation flow, which makes the equipment size too large.
中国专利:用于反应堆紧急停堆时的热管散热器,针对陆上分散式布置反应堆,采用分离式热管作为反应堆紧急停堆后对安全壳内气体冷却,采用大气作为最终热阱。而本专利针对一体化反应堆,对反应堆冷却剂进行冷却,采用海水作为最终热阱。Chinese patent: Heat pipe radiator for reactor emergency shutdown. For land-based distributed reactors, separate heat pipes are used to cool the gas in the containment after reactor emergency shutdown, and the atmosphere is used as the final heat sink. But this patent is aimed at the integrated reactor, cools the reactor coolant, and uses seawater as the final heat sink.
中国专利:浮动核电站非能动余热排出系统,针对分散式布置浮动核电站反应堆,将一回路冷却剂系统与海水水箱直接相连,将海水作为最终热阱。而本专利针对一体化反应堆,采用分离式热管回路建立在冷却剂系统和海水间的中间回路,可保证冷却剂与海水的隔离。Chinese patent: Passive waste heat removal system for floating nuclear power plants. Aiming at the decentralized layout of floating nuclear power plant reactors, the primary coolant system is directly connected to the sea water tank, and sea water is used as the final heat sink. However, this patent is aimed at the integrated reactor, and uses a separate heat pipe circuit to establish an intermediate circuit between the coolant system and seawater, which can ensure the isolation of the coolant from the seawater.
中国专利:一种基于热管的乏燃料池非能动余热导出系统和中国专利:基于水冷热管的乏燃料非能动余热导出系统,均采用热管对乏燃料池进行非能动余热排出,以大气作为最终热阱。而本专利为针对一体化反应堆系统的余热排出系统,以海水为最终热阱,针对的对象间无直接联系,结构上有很大的差异。Chinese patent: a heat pipe-based passive waste heat export system for spent fuel pools and a Chinese patent: a spent fuel passive heat export system based on water-cooled heat pipes, both use heat pipes to discharge passive waste heat from spent fuel pools, using the atmosphere as the final heat trap. However, this patent is aimed at the waste heat discharge system of the integrated reactor system, with seawater as the final heat sink, and there is no direct connection between the objects targeted, and there are great differences in structure.
中国专利:压水堆核电站分离式热管式非能动余热排出系统,针对分散式布置的陆上核电站,将蒸汽发生器与热管蒸发段的壳侧相连,通过两个回路的相变换热将热量传至最终热阱大气。而本专利针对一体化反应堆,将冷却剂系统与分离式热管回路相连,将海水作为最终热阱,减少了中间传热回路且避免了因蒸汽发生器故障导致余热无法排出的可能性。Chinese patent: Separated heat pipe passive waste heat removal system for pressurized water reactor nuclear power plants. For distributed land nuclear power plants, the steam generator is connected to the shell side of the heat pipe evaporation section, and the heat is transferred through the phase conversion of the two circuits. to the final heat sink atmosphere. However, this patent is aimed at the integrated reactor, connecting the coolant system with the separate heat pipe circuit, using seawater as the final heat sink, reducing the intermediate heat transfer circuit and avoiding the possibility that the waste heat cannot be discharged due to the failure of the steam generator.
发明内容Contents of the invention
本发明的目的是为了提供一种基于分离式热管的一体化压水堆非能动余热排出系统,是一种以分离式热管为中间回路,针对一体化压水堆的非能动余热排出系统。The purpose of the present invention is to provide an integrated PWR passive waste heat removal system based on separated heat pipes, which is a passive waste heat removal system for integrated PWRs with separated heat pipes as the intermediate circuit.
本发明的目的是这样实现的:包括主冷却剂系统、热交换器、热管冷凝段,主冷却剂系统的上充通道通过冷却剂下降管与热交换器的壳侧出口连接,主冷却剂系统的下泄通道通过冷却剂上升管与热交换器的壳侧入口连接,热交换器的蒸发段管束入口联箱通过下降管与热管冷凝段的出口联箱连接,热交换器的蒸发段管束出口联箱通过上升管与热管冷凝段的入口联箱连接,热管冷凝段上端设置有释放阀,冷却剂上升管上设置有常开隔离阀,冷却剂下降管上设置有非能动隔离阀。The object of the present invention is achieved like this: comprise main coolant system, heat exchanger, heat pipe condensing section, the upper filling channel of main coolant system is connected with the shell side outlet of heat exchanger through coolant downcomer, main coolant system The drain channel of the heat exchanger is connected to the shell-side inlet of the heat exchanger through the coolant riser pipe, the inlet header of the tube bundle of the evaporating section of the heat exchanger is connected to the outlet header of the condensing section of the heat pipe through the downcomer, and the outlet header of the tube bundle of the evaporating section of the heat exchanger is connected The tank is connected to the inlet header of the condensing section of the heat pipe through the riser pipe. The upper end of the condensing section of the heat pipe is provided with a release valve.
本发明还包括这样一些结构特征:The present invention also includes such structural features:
1.冷却剂自热交换器的壳侧出口流出后,依次流经主冷却剂系统的上充通道、冷却剂下降管、主冷却剂系统的压力容器下降段、主冷却剂系统的反应堆堆芯通道、主冷却剂系统的压力容器上升段、主冷却剂系统的下泄通道、冷却剂上升管后进入热交换器的壳侧入口,形成闭合余热导出回路一。1. After the coolant flows out from the shell side outlet of the heat exchanger, it flows through the top-fill channel of the main coolant system, the coolant downcomer, the pressure vessel down section of the main coolant system, and the reactor core of the main coolant system The channel, the ascending section of the pressure vessel of the main coolant system, the drain channel of the main coolant system, and the coolant ascending pipe enter the shell-side inlet of the heat exchanger to form a closed waste heat export circuit 1.
2.热管工作介质依次流经热交换器管侧、上升管、热管冷凝段管侧、下降管、热交换器管侧形成闭合余热导出回路二,所述热管工作介质是一种载热工质,包括水或纳米流体。2. The working medium of the heat pipe flows through the tube side of the heat exchanger, the ascending tube, the tube side of the condensing section of the heat pipe, the downcomer, and the tube side of the heat exchanger to form a closed waste heat export circuit 2. The working medium of the heat pipe is a heat-carrying working medium , including water or nanofluids.
3.所述热交换器为管壳式换热器,且壳侧流体为冷却剂,管侧流体为热管工作介质。3. The heat exchanger is a shell-and-tube heat exchanger, and the fluid on the shell side is the coolant, and the fluid on the tube side is the working medium of the heat pipe.
与现有技术相比,本发明的有益效果是:本发明所述的一种基于分离式热管的一体化压水堆非能动余热排出系统,其采用了分离式热管作为主冷却剂系统和最终热阱的中间传热回路,依靠两相流自然循环驱动系统,提高系统的固有安全性。同时这样的设计避免了冷却剂与海水直接接触,有效保证对冷却剂的屏蔽,另一方面在引入小热阻的情况下实现了较长距离的热量传递,简化了系统设计,减小了设备尺寸,从而满足一体化压水堆特殊应用环境的需求。也即本发明在提高系统固有安全性的同时,保证对反应堆冷却剂的隔离、满足较长距离热量传递需求并简化系统设计。Compared with the prior art, the beneficial effect of the present invention is: the integrated PWR passive waste heat removal system based on the separated heat pipe according to the present invention adopts the separated heat pipe as the main coolant system and the final The intermediate heat transfer loop of the heat sink relies on the natural circulation of the two-phase flow to drive the system, which improves the inherent safety of the system. At the same time, this design avoids direct contact between the coolant and seawater, effectively ensuring the shielding of the coolant. On the other hand, it realizes heat transfer over a long distance with the introduction of small thermal resistance, which simplifies the system design and reduces the equipment cost. size, so as to meet the requirements of the special application environment of the integrated pressurized water reactor. That is to say, while improving the inherent safety of the system, the present invention ensures the isolation of the reactor coolant, satisfies the requirement of long-distance heat transfer and simplifies the system design.
附图说明Description of drawings
图1是本发明的结构示意图。Fig. 1 is a structural schematic 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.
如图1所示的本发明的技术方案一种基于分离式热管的一体化压水堆非能动余热排出系统,包括非能动余热导出系统和分离式热管回路系统。As shown in Figure 1, the technical solution of the present invention is an integrated PWR passive waste heat removal system based on separate heat pipes, including a passive waste heat export system and a separate heat pipe loop system.
本发明所针对的一体化反应堆主冷却剂系统的冷却剂流动通道主要由反应堆堆芯通道1,冷却剂上升段2,,蒸汽发生器5、冷却剂下降段6组成,附图中标记3为系统稳压空间。非能动余热导出系统除主冷却剂系统还包括冷却剂上升管12,非能动余热排出热交换器(热管蒸发段)13和冷却剂下降管11;非能动余热排出热交换器13为余热导出系统和热管回路系统共用设备;分离式热管回路系统由非能动余热排出热交换器13,上升管15,分离式热管冷凝段14以及下降管16组成;所述分离式热管冷凝段14置于舱外海水中。The coolant flow channel of the integrated reactor main coolant system aimed at by the present invention is mainly composed of a reactor core channel 1, a coolant ascending section 2, a steam generator 5, and a coolant descending section 6, and the mark 3 in the accompanying drawings is System voltage stabilization space. In addition to the main coolant system, the passive waste heat export system also includes a coolant riser 12, a passive waste heat discharge heat exchanger (heat pipe evaporation section) 13 and a coolant downcomer 11; the passive waste heat discharge heat exchanger 13 is the waste heat export system Shared equipment with the heat pipe circuit system; the separated heat pipe circuit system is composed of a passive waste heat discharge heat exchanger 13, an ascending pipe 15, a separated heat pipe condensing section 14 and a descending pipe 16; the separated heat pipe condensing section 14 is placed outside the cabin in sea water.
非能动余热排出热交换器13为管壳式换热器,壳侧流体为冷却剂,管侧流体为热管工作介质;为非能动余热导出系统与热管回路系统共用设备,放置在反应堆堆舱室中。热交换器13壳侧流体为反应堆冷却剂,壳侧入口通过冷却剂上升管12与主冷却剂系统4下泄通道相联;壳侧出口通过冷却剂下降管11与主冷却剂系统4的上充通道相联。热交换器13管侧为分离式热管蒸发段,蒸发段管束入口联箱19通过下降管16与冷凝段14出口联箱20相联,蒸发段管束出口联箱18通过上升管与冷凝段14入口联箱21相联。冷却剂上升管12上设常开隔离阀9,所述的冷却剂下降管11上设有非能动隔离阀10。The passive waste heat discharge heat exchanger 13 is a shell-and-tube heat exchanger, the fluid on the shell side is the coolant, and the fluid on the tube side is the working medium of the heat pipe; it is a common equipment for the passive waste heat export system and the heat pipe circuit system, and is placed in the reactor cabin . The shell side fluid of the heat exchanger 13 is the reactor coolant, and the shell side inlet is connected with the main coolant system 4 drain channel through the coolant riser 12; Channels are connected. The tube side of the heat exchanger 13 is a separated heat pipe evaporating section, the tube bundle inlet header 19 of the evaporating section is connected with the outlet header 20 of the condensing section 14 through the downcomer 16, and the tube bundle outlet header 18 of the evaporating section is connected with the inlet of the condensing section 14 through the rising tube Header 21 is connected. A normally open isolation valve 9 is provided on the coolant rising pipe 12 , and a passive isolation valve 10 is provided on the coolant down pipe 11 .
所述的非能动余热排出热交换器13放置在反应堆舱室中,壳侧出口处海拔高度高于下降管11与主冷却剂上充通道接口;所述的分离式热管冷凝段14置于舱外的海水舱室中,海拔高度低于海平面,冷凝段14上端装有释放阀17。The passive waste heat discharge heat exchanger 13 is placed in the reactor cabin, and the altitude of the outlet on the shell side is higher than the interface between the downcomer 11 and the main coolant charging channel; the separated heat pipe condensing section 14 is placed outside the cabin In the seawater cabin, the altitude is lower than the sea level, and the upper end of the condensation section 14 is equipped with a release valve 17.
换热器管侧为分离式热管蒸发段,蒸发段由多管束组成,端口进出口联箱通过下降管、上升管与冷凝段进出口联箱相联。The tube side of the heat exchanger is a separated heat pipe evaporating section, the evaporating section is composed of multiple tube bundles, and the inlet and outlet headers of the port are connected with the inlet and outlet headers of the condensing section through downcomers and risers.
非能动余热导出系统中主冷却剂自非能动余热排出热交换器13壳侧出口流出后,依次流经主冷却剂系统上充通道、冷却剂下降管11、压力容器下降段6、反应堆堆芯通道1,压力容器上升段2、主冷却剂系统下泄通道、冷却剂上升管12进入热交换器13壳侧入口形成闭合余热导出回路一。分离式热管回路中工作介质依次流经热交换器13管侧、上升管15、热管冷凝段14和下降管16,再返回热交换器13管侧,形成闭合余热导出回路二,热管回路内工作介质为水或纳米流体等其它载热工质。After the main coolant in the passive waste heat export system flows out from the shell-side outlet of the passive waste heat discharge heat exchanger 13, it flows through the main coolant system upfill channel, coolant downcomer 11, pressure vessel down section 6, and reactor core in sequence. Channel 1, rising section 2 of the pressure vessel, main coolant system drain channel, and coolant rising pipe 12 enter the heat exchanger 13 shell-side inlet to form a closed waste heat export circuit 1. In the separated heat pipe circuit, the working medium flows through the tube side of the heat exchanger 13, the ascending pipe 15, the condensing section 14 of the heat pipe, and the downcomer 16 in sequence, and then returns to the tube side of the heat exchanger 13 to form a closed waste heat export circuit 2, which works in the heat pipe circuit The medium is other heat-carrying working fluids such as water or nanofluid.
本发明所述的一种基于分离式热管的一体化压水堆非能动余热排出系统的工作原理是:一体化反应堆系统停堆后,主泵进入惰转过程至完全停转,隔离阀10自动开启,余热排出系统投入使用。冷却剂由压力容器下封头流入堆芯通道1吸收热量,温度升高,向上运动流经压力容器上升段2后通过下泄通道进入冷却剂上升管12,而后进入非能动余热排出热交换器13壳侧。而热交换器13的管侧为分离式热管回路的蒸发段,进入热交换器13壳侧的冷却剂被冷却,向下流动,通过冷却剂下降管11由主冷却剂系统上充通道进入压力容器下降段6,回到压力容器下封头,这样形成自然循环,将堆芯余热传递热管回路蒸发段即热交换器13管侧。热交换器13管侧工作介质吸收热量蒸发后向上运动,进入联箱18,通过上升管15进入热管回路冷凝段14。在冷凝段14中工作介质被管外海水冷凝,在重力作用下进入联箱20,而后通过下降管16回到热交换器13,构成闭合的余热导出回路。在冷凝段14的管外,由于海水吸收热量向上运动形成对流,堆芯余热最终传递至海水。The working principle of the integrated pressurized water reactor passive waste heat removal system based on separate heat pipes of the present invention is: after the integrated reactor system shuts down, the main pump enters the process of idling until it stops completely, and the isolation valve 10 automatically On, the waste heat removal system is put into use. The coolant flows from the lower head of the pressure vessel into the core channel 1 to absorb heat, the temperature rises, moves upwards, flows through the rising section 2 of the pressure vessel, enters the coolant riser 12 through the downflow channel, and then enters the passive waste heat discharge heat exchanger 13 shell side. The tube side of the heat exchanger 13 is the evaporation section of the separated heat pipe circuit. The coolant entering the shell side of the heat exchanger 13 is cooled, flows downward, and enters the pressure from the upper charging channel of the main coolant system through the coolant down pipe 11. The descending section 6 of the vessel returns to the lower head of the pressure vessel, thus forming a natural circulation to transfer the waste heat of the core to the evaporating section of the heat pipe circuit, that is, the tube side of the heat exchanger 13 . The working medium on the tube side of the heat exchanger 13 absorbs heat and evaporates, moves upwards, enters the header 18 , and enters the condensation section 14 of the heat pipe circuit through the riser 15 . In the condensation section 14, the working medium is condensed by the seawater outside the pipe, enters the header 20 under the action of gravity, and then returns to the heat exchanger 13 through the downcomer 16, forming a closed waste heat export circuit. Outside the tube of the condensing section 14 , since the seawater absorbs heat and moves upward to form convection, the waste heat of the core is finally transferred to the seawater.
本发明采用了分离式热管作为主冷却剂系统和最终热阱的中间传热回路,依靠密度差自然循环驱动系统,提高系统的固有安全性。同时这样的设计避免了冷却剂与海水直接接触,有效保证对冷却剂的屏蔽,另一方面在引入小热阻的情况下实现了较长距离的热量传递,简化了系统设计,减小了设备尺寸,从而满足一体化压水堆特殊应用环境的需求。The invention adopts the separated heat pipe as the intermediate heat transfer circuit between the main coolant system and the final heat sink, relies on the density difference to drive the system in natural circulation, and improves the inherent safety of the system. At the same time, this design avoids direct contact between the coolant and seawater, effectively ensuring the shielding of the coolant. On the other hand, it realizes heat transfer over a long distance with the introduction of small thermal resistance, which simplifies the system design and reduces the equipment cost. size, so as to meet the requirements of the special application environment of the integrated pressurized water reactor.
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Cited By (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107146925A (en) * | 2017-06-16 | 2017-09-08 | 苏州热工研究院有限公司 | Passive exhaust for battery compartment |
| CN107393605A (en) * | 2017-07-07 | 2017-11-24 | 西安交通大学 | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor |
| CN107833642A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | Heat exchanger is located at the outer marine PWR Passive residual heat removal system of water tank |
| CN107833641A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | A kind of marine PWR seawater cools down Passive residual heat removal system |
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| CN110957055A (en) * | 2019-10-09 | 2020-04-03 | 中国核电工程有限公司 | A separate flexible heat pipe cooling system suitable for pressurized water reactor nuclear power plants |
| CN111785399A (en) * | 2020-07-06 | 2020-10-16 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | System for heat export of marine nuclear power platform |
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| CN114334193A (en) * | 2021-12-27 | 2022-04-12 | 西安交通大学 | Separated heat pipe reactor |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20130343504A1 (en) * | 2012-06-20 | 2013-12-26 | Korea Atomic Energy Research Institute | Heat exchanger for passive residual heat removal system |
| CN103903659A (en) * | 2014-03-28 | 2014-07-02 | 哈尔滨工程大学 | Passive waste heat removal system for floating nuclear power plant |
| CN104520939A (en) * | 2012-06-13 | 2015-04-15 | 西屋电气有限责任公司 | Small modular reactor safety systems |
| CN104916334A (en) * | 2015-06-11 | 2015-09-16 | 哈尔滨工程大学 | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant |
| CN104969301A (en) * | 2013-02-27 | 2015-10-07 | 西屋电气有限责任公司 | Pressurized water reactor depressurization system |
-
2017
- 2017-01-24 CN CN201710053771.0A patent/CN106816186A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104520939A (en) * | 2012-06-13 | 2015-04-15 | 西屋电气有限责任公司 | Small modular reactor safety systems |
| US20130343504A1 (en) * | 2012-06-20 | 2013-12-26 | Korea Atomic Energy Research Institute | Heat exchanger for passive residual heat removal system |
| CN104969301A (en) * | 2013-02-27 | 2015-10-07 | 西屋电气有限责任公司 | Pressurized water reactor depressurization system |
| CN103903659A (en) * | 2014-03-28 | 2014-07-02 | 哈尔滨工程大学 | Passive waste heat removal system for floating nuclear power plant |
| CN104916334A (en) * | 2015-06-11 | 2015-09-16 | 哈尔滨工程大学 | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant |
Cited By (25)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
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| CN107146925B (en) * | 2017-06-16 | 2020-04-17 | 苏州热工研究院有限公司 | Passive exhaust device for storage battery compartment |
| CN107393605A (en) * | 2017-07-07 | 2017-11-24 | 西安交通大学 | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor |
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| CN110957055A (en) * | 2019-10-09 | 2020-04-03 | 中国核电工程有限公司 | A separate flexible heat pipe cooling system suitable for pressurized water reactor nuclear power plants |
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