CN101266843B - Siphon breaker - Google Patents
Siphon breaker Download PDFInfo
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- CN101266843B CN101266843B CN2007100870086A CN200710087008A CN101266843B CN 101266843 B CN101266843 B CN 101266843B CN 2007100870086 A CN2007100870086 A CN 2007100870086A CN 200710087008 A CN200710087008 A CN 200710087008A CN 101266843 B CN101266843 B CN 101266843B
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- sodium
- pipe
- reactor
- protective sleeve
- return pipe
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- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims abstract description 58
- 229910052708 sodium Inorganic materials 0.000 claims abstract description 58
- 239000011734 sodium Substances 0.000 claims abstract description 58
- 230000001681 protective effect Effects 0.000 claims abstract description 17
- 238000002955 isolation Methods 0.000 claims abstract description 5
- 235000021023 sodium intake Nutrition 0.000 claims abstract 4
- 238000011161 development Methods 0.000 abstract description 3
- 230000006378 damage Effects 0.000 abstract description 2
- 239000007788 liquid Substances 0.000 description 9
- 238000000605 extraction Methods 0.000 description 8
- 239000007789 gas Substances 0.000 description 7
- 238000000746 purification Methods 0.000 description 5
- 238000013461 design Methods 0.000 description 3
- 238000002474 experimental method Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 238000009825 accumulation Methods 0.000 description 1
- 239000000443 aerosol Substances 0.000 description 1
- 239000008358 core component Substances 0.000 description 1
- 230000001934 delay Effects 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 230000009916 joint effect Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000010355 oscillation Effects 0.000 description 1
- 230000010349 pulsation Effects 0.000 description 1
- 238000004088 simulation Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- 230000005514 two-phase flow Effects 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
Images
Classifications
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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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
本发明提供了一种结构简单、安全可靠,在发生堆外管道破裂事故时,减少钠泄漏量、延缓事故的发展速度以便操作人员有足够时间进行处理的虹吸破坏装置。该装置包括取钠管通过堆外管道与循环泵连接,循环泵的另一端通过堆外管道与回钠管连接,取钠管、回钠管固定在隔离板上,分别伸入到堆内两个保护套管中,进口孔板位于取钠管的下端,所述的取钠管伸入的保护套管的断口结构为文丘里管,并在其四周开有4个中孔;所述进口孔板的孔径为45mm;降低取钠管的标高。
The invention provides a siphon destruction device that is simple in structure, safe and reliable, and can reduce the amount of sodium leakage and delay the development of the accident so that operators have enough time to deal with it when an accident occurs due to pipe rupture outside the reactor. The device includes a sodium intake pipe connected to a circulation pump through a pipe outside the reactor. The other end of the circulation pump is connected to a sodium return pipe through a pipe outside the reactor. The sodium intake pipe and sodium return pipe are fixed on the isolation plate and extend into two sides of the reactor respectively. In a protective sleeve, the inlet orifice plate is located at the lower end of the sodium pipe. The fracture structure of the protective sleeve that the sodium pipe extends into is a venturi tube, and four middle holes are opened around it; the inlet The hole diameter of the orifice plate is 45mm; lower the elevation of the sodium tube.
Description
技术领域technical field
本发明涉及流量的附加调整装置领域,特别涉及一种虹吸破坏装置。The invention relates to the field of additional adjustment devices for flow, in particular to a siphon breaking device.
背景技术Background technique
反应堆一次钠采用堆外净化方式,净化回路中的大部分管道和设备的标高低于反应堆容器内钠液位标高。一旦堆外管道发生破裂,池内高温、高放射性的液钠将在堆内压力和虹吸力共同作用下从管道破口喷出,形成失钠事故。这不仅对反应堆的自身安全构成威胁,而且随液钠排出的高放射性气体溶胶将严重污染周围环境。The primary sodium of the reactor is purified outside the reactor, and the elevation of most of the pipes and equipment in the purification circuit is lower than that of the sodium liquid level in the reactor vessel. Once the pipeline outside the reactor breaks, the high-temperature and highly radioactive liquid sodium in the pool will be ejected from the pipeline breach under the joint action of the reactor pressure and siphon force, resulting in a sodium loss accident. This not only poses a threat to the safety of the reactor itself, but also the highly radioactive aerosol discharged with the liquid sodium will seriously pollute the surrounding environment.
国际上仅俄罗斯提出过池式快堆非能动虹吸破坏装置初步设计,但尚未经实验验证和工程应用。通过实验发现此设计在净化回路正常运行和发生堆外管道大破口失钠事故时,其性能不能满足设计要求,其表现在:(1)当净化流量≥5m3/h时,净化回路回钠管段(堆内)出口环腔顶部产生气液两相沫状溢流,并直接掉落到热钠池高温液钠自由面上;(2)当净化流量≥5m3/h时,净化回路回钠管段保护套管的下降管中产生大量气体夹带,在换料液位时,其气体体积含量高达30%左右,这些被夹带的气体一旦经冷池和主循环泵而进入堆芯,将造成反应堆功率振荡、传热恶化和循环泵的汽蚀等严重问题。另外,由于气体可能在冷池中积聚和破裂而产生压力脉动并诱发堆内构件和堆芯组件的流致振动,严重影响反应堆的安全运行;(3)发生净化回路堆外管道破口失钠事故时,钠泄漏量偏大,有可能使事故冷却器(独立热交换器)的钠进口裸露在气体中,而影响它的正常工作,使反应堆的余热无法排出而产生严重后果;(4)发生破口失钠事故时,系统缺乏有效的人为干预措施,使事故尽早结束,而只能顺其自然终止。Internationally, only Russia has proposed the preliminary design of the passive siphon breaker for pool-type fast reactors, but it has not yet been verified by experiments and applied in engineering. Through experiments, it is found that the performance of this design cannot meet the design requirements when the purification circuit is in normal operation and the accident of sodium loss from a large breach in the external reactor pipeline occurs. A gas-liquid two-phase foamy overflow occurs at the top of the outlet ring cavity of the pipe section (in the stack), and falls directly onto the free surface of the high-temperature liquid sodium in the hot sodium pool; (2) When the purification flow rate is ≥5m 3 /h, the purification circuit returns to A large amount of gas is entrained in the downcomer of the protective casing of the sodium pipe section. At the refueling level, the gas volume content is as high as 30%. Once the entrained gas enters the core through the cold pool and the main circulation pump, it will cause Serious problems such as reactor power oscillations, heat transfer deterioration, and cavitation of circulation pumps. In addition, due to the possible accumulation and rupture of gas in the cold pool, pressure pulsation will be generated and flow-induced vibration of reactor internals and core components will be induced, which will seriously affect the safe operation of the reactor; During the accident, the leakage of sodium was too large, which may expose the sodium inlet of the accident cooler (independent heat exchanger) to the gas, affecting its normal operation, and causing serious consequences due to the inability to discharge the waste heat of the reactor; (4) When a sodium loss accident occurs through a breach, the system lacks effective human intervention measures to make the accident end as soon as possible, but it can only be terminated naturally.
发明内容Contents of the invention
本发明克服了现有技术中的缺点,提供一种结构简单、安全可靠,在发生堆外管道破裂事故时,减少钠泄漏量、延缓事故的发展速度以便操作人员有足够时间进行处理的虹吸破坏装置。The present invention overcomes the shortcomings in the prior art, and provides a simple structure, safe and reliable siphon breakage that reduces the amount of sodium leakage and delays the development of the accident in the event of an accident of a pipeline rupture outside the reactor, so that the operator has enough time to deal with it device.
为了解决上述技术问题,本发明是通过以下技术方案实现的:该装置包括取钠管通过堆外管道与循环泵连接,循环泵的另一端通过堆外管道与回钠管连接,取钠管、回钠管固定在隔离板上,分别伸入到堆内两个保护套管中,进口孔板位于取钠管的下端,所述的取钠管伸入的保护套管的断口结构为文丘里管,并在其四周开有4个中孔;所述进口孔板的孔径为45mm;降低取钠管的标高。In order to solve the above-mentioned technical problems, the present invention is achieved through the following technical proposals: the device comprises a sodium pipe that is connected to a circulation pump through a pipeline outside the pile, and the other end of the circulation pump is connected with a sodium return pipe through a pipeline outside the pile, and the sodium pipe, The sodium return pipe is fixed on the isolation plate and extends into the two protective sleeves in the stack respectively. The inlet orifice is located at the lower end of the sodium extraction pipe. The fracture structure of the protective sleeve where the sodium extraction pipe extends is Venturi pipe, and have 4 middle holes around it; the aperture of the inlet orifice plate is 45mm; reduce the elevation of the sodium pipe.
为了使系统能够更稳定运行,消除气液两相溢流和夹带气体问题,更好的起到安全保护作用,本发明还可以:所述的回钠管的出口接头的垂直开口盲死,在盲板中心开一个6mm的小孔,同时在高于盲板5~7mm的回钠管侧面周向均匀地开16个10mm侧面孔。所述的回钠管的保护套管出口处增加一个40mm的孔板。所述的文丘里管喉部直径为50mm。所述的中孔直径为20mm。所述的堆外管道为双层管。In order to enable the system to operate more stably, eliminate the problems of gas-liquid two-phase overflow and entrained gas, and better play a role in safety protection, the present invention can also: the vertical opening of the outlet joint of the sodium return pipe is blinded, A small hole of 6 mm is opened in the center of the blind plate, and 16 side holes of 10 mm are uniformly opened in the circumferential direction of the sodium return pipe 5-7 mm higher than the blind plate. Add a 40mm orifice plate at the outlet of the protective sleeve of the sodium return pipe. The throat diameter of the Venturi tube is 50mm. The diameter of the middle hole is 20mm. The pipeline outside the pile is a double-layer pipeline.
与现有技术相比,本发明的优点是:成功的解决了反应堆大尺度系统发生净化管路大破口时的复杂两相流动现象,在发生堆外管道破裂事故时,以非能动方式使钠泄漏量减少、事故的发展速度延缓使操作人员有足够的时间进行处理,降低事故的后果。Compared with the prior art, the present invention has the advantages of successfully solving the complex two-phase flow phenomenon when a large breach in the purification pipeline occurs in the large-scale reactor system, and making the sodium The reduction in leakage and the delay in the development of accidents allow operators to have enough time to deal with them and reduce the consequences of accidents.
附图说明Description of drawings
图1虹吸破坏装置模拟流程图Fig.1 Simulation flow chart of siphon breaking device
图2回钠管出口接头结构剖视图Fig. 2 Structural sectional view of the outlet joint of the sodium return pipe
图3取钠管口结构剖视图Fig. 3 takes the sectional view of the structure of the sodium nozzle
图中:取钠管1 回钠管2 保护套管3 保护套管4 进口孔板5 堆外管道6 循环泵7 出口接头8 小孔9 侧面孔10 文丘里管11中孔12 隔离板13In the figure: Sodium extraction pipe 1
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:Below in conjunction with accompanying drawing and specific embodiment the present invention is described in further detail:
该装置包括取钠管1通过堆外管道6与循环泵7连接,循环泵7的另一端通过堆外管道6与回钠管2连接,取钠管1与回钠管2分别固定在隔离板13上,取钠管1伸入到堆内保护套管3中,回钠管伸入到保护套管4中,进口孔板5位于取钠管1的下端,所述的取钠管1伸入的保护套管3的断口结构为喉部直径为50mm的文丘里管11,并在其四周开有4个20mm的中孔12。所述进口孔板5的孔径为45mm。降低取钠管1的标高。所述的的回钠管2出口接头8的垂直开口盲死,在盲板中心开一个直径为6mm的小孔9,同时在高于盲板5~7mm的回钠管2侧面周向均匀地开16个直径为10mm的侧面孔10;在回钠管2的保护套管4出口处增加一个40mm的孔板;所述的堆外管道6为双层管。The device comprises that the sodium extraction pipe 1 is connected with the circulation pump 7 through the
由于取钠管1与保护套管3形成环隙,其液位在正常运行时低于取钠管1中的液位,在堆外管道6发生双端断裂时,钠液从取钠管1大量流出,造成保护套管3内的钠流速迅速增加,和阻力增大,使环隙液位迅速降到断口标高,气腔气体从断口流出,压力迅速下降,这样,造成进口孔板5处的钠流减少,从而中止钠的进一步泄漏,起到虹吸破坏的安全保护作用。Because the sodium pipe 1 and the
Claims (4)
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CN2007100870086A CN101266843B (en) | 2007-03-14 | 2007-03-14 | Siphon breaker |
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CN101266843A CN101266843A (en) | 2008-09-17 |
CN101266843B true CN101266843B (en) | 2011-01-12 |
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CN119197997A (en) * | 2024-11-27 | 2024-12-27 | 上海核工程研究设计院股份有限公司 | Test system and test method for verifying the reverse discharge capability of siphon breaking device under low pressure |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3784443A (en) * | 1970-08-07 | 1974-01-08 | Commissariat Energie Atomique | Device for the leak-tight assembly of heat exchangers in nuclear reactors |
US5263066A (en) * | 1991-11-06 | 1993-11-16 | Commissariat A L'energie Atomique | Nuclear reactor equipped with a core catcher |
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2007
- 2007-03-14 CN CN2007100870086A patent/CN101266843B/en active Active
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3784443A (en) * | 1970-08-07 | 1974-01-08 | Commissariat Energie Atomique | Device for the leak-tight assembly of heat exchangers in nuclear reactors |
US5263066A (en) * | 1991-11-06 | 1993-11-16 | Commissariat A L'energie Atomique | Nuclear reactor equipped with a core catcher |
Non-Patent Citations (3)
Title |
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JP特开平8-146174A 1996.06.07 |
JP特开平8-285974A 1996.11.01 |
张东辉.中国实验快堆一次钠泄漏防御的改进及其效果分析.核动力工程.2008,(8),282-285. * |
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