WO2014090100A1 - Inlet pipeline structure of residual heat removal system capable of avoiding phenomenon of "dead pipeline" - Google Patents

Inlet pipeline structure of residual heat removal system capable of avoiding phenomenon of "dead pipeline" Download PDF

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Publication number
WO2014090100A1
WO2014090100A1 PCT/CN2013/088412 CN2013088412W WO2014090100A1 WO 2014090100 A1 WO2014090100 A1 WO 2014090100A1 CN 2013088412 W CN2013088412 W CN 2013088412W WO 2014090100 A1 WO2014090100 A1 WO 2014090100A1
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Prior art keywords
pipe section
pipeline
dead
pipe
waste heat
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PCT/CN2013/088412
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French (fr)
Chinese (zh)
Inventor
任云
赖建永
苏荣福
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中国核动力研究设计院
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Publication of WO2014090100A1 publication Critical patent/WO2014090100A1/en
Priority to ZA2015/04981A priority Critical patent/ZA201504981B/en

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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
    • 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 field of pipeline arrangement of a pressurized water reactor nuclear power plant, and particularly relates to an inlet pipe structure of a waste heat discharge system capable of avoiding a "dead pipe” phenomenon.
  • the residual heat removal system is connected to the reactor coolant system and is mainly used to discharge the residual heat of the core during shutdown. It is one of the important auxiliary systems for the pressurized water reactor nuclear power plant.
  • the inlet is connected to the main pipe hot section of the reactor coolant system via two isolation valves. During normal operation of the nuclear power plant, the isolation valve at the inlet of the residual heat removal system is closed, and the pipeline between the two isolation valves forms a low-pressure "dead pipe" that does not flow. In the existing nuclear power plant design, there is a lack of effective measures to increase the pressure in the "dead pipe".
  • the high temperature coolant of the reactor coolant system continuously heats the liquid in the "dead pipe” through the first isolation valve, which will result in “death.”
  • the internal liquid temperature of the pipeline exceeds the corresponding saturation temperature at the pressure at which it is located, causing partial boiling.
  • the impurities accumulate at the water/vapor interface, causing serious corrosion to the valve gate and affecting the sealing of the valve. This phenomenon is known as the “dead pipeline” phenomenon, which seriously threatens the safety of nuclear power plants.
  • the technical problem to be solved by the present invention is to provide an increase in the pressure in the "dead pipe” and the saturation temperature of the coolant in the "dead pipe", thereby avoiding the vaporization of the coolant in the "dead pipe” and solving the "dead pipe”.
  • the problem at the same time, will not increase the pipeline layout structure during the operation of the nuclear power plant due to such an arrangement.
  • the technical solution of the present invention is an inlet pipe structure of a waste heat discharge system capable of avoiding a "dead pipe” phenomenon, which is disposed between a reactor heat pipe section and a cold pipe section.
  • the invention comprises a waste heat discharge system pipe section connecting the heat pipe section and the cold pipe section, and a dead pipeline valve group pipe section disposed on the waste heat discharge system pipe section;
  • the dead pipeline valve group pipe section includes a first isolation valve and a second isolation valve, wherein the first isolation valve and the second isolation valve are arranged in series on a waste heat removal system pipe; the first isolation valve and the second isolation valve
  • the pipe section between the waste heat exhaust system piping is a dead pipe section;
  • the dead pipeline valve group pipe section further includes a bypass line, a manual isolation valve disposed on the bypass line, and one end of the bypass line is connected to the pipe section of the waste heat discharge system pipe near the heat pipe section, and the other end is connected Go to the dead pipe section.
  • Two ends of the bypass line are respectively provided with a first restrictor and a second restrictor.
  • the first restrictor and the second restrictor are both 3 mm restrictors.
  • the bypass line has an inner diameter of ⁇ , and the bypass line 304 has a length of 400 to 1000 ⁇ .
  • the utility model further comprises a waste heat discharge pump and a waste heat discharge heat exchanger disposed on the pipe section of the waste heat discharge system; the dead pipe valve group pipe section, the residual heat discharge pump and the waste heat discharge heat exchanger are arranged in order from the heat pipe section to the cold pipe section.
  • the first isolation valve and the second isolation valve are in a closed state, and the manual isolation valve is in an open state.
  • the invention can increase the pressure in the "dead pipeline” to the operating pressure of the reactor coolant system, increase the saturation temperature of the liquid in the "dead pipeline”, avoid the appearance of vaporization, and solve the "dead pipeline” problem;
  • the present invention can effectively limit the loss of the reactor coolant water volume caused by the bypass pipe rupture or the leakage of the second isolation valve, so that it does not threaten the safety of the nuclear power plant; (3) The present invention can effectively limit the temperature of the coolant flowing into the residual heat discharge system due to the leakage of the second isolation valve without impairing the integrity of the waste heat removal system.
  • FIG. 1 is a schematic view showing the structure of an inlet pipe of a waste heat removal system capable of avoiding a "dead pipe” phenomenon
  • Figure 2 is an enlarged schematic view of the broken line block diagram of Figure 1.
  • the nuclear power plant reactor includes a primary circuit system including a plurality of loops, generally two or three loops; each loop includes a heat pipe section 1 and a cold pipe section 6;
  • the pump enters the pressure vessel from the cold pipe section 6 and draws heat from the core.
  • the coolant after the heat is removed from the pressure vessel, the heat is released from the heat pipe section 1 through the steam generator, and the heat released by the coolant returns to the cold pipe section 6 and then enters again.
  • a waste heat removal system is disposed between the heat pipe section 1 and the cold pipe section 6 of the loop, including a waste heat discharge system pipe 2 connecting the heat pipe section 1 and the cold pipe section 6, and an automatic heat pipe section 1 a dead pipeline valve group pipe section 3, a residual heat discharge pump 4 and a residual heat discharge heat exchanger 5 arranged in the direction of the cold pipe section 6;
  • the dead pipeline valve group pipe section 3 includes a first isolation valve 301 and a second isolation valve 302, and the first isolation valve 301 and the second isolation valve 302 are arranged in series on the waste heat removal system pipe 2;
  • the pipe section of the residual heat discharge system pipe 2 between the first isolation valve 301 and the second isolation valve 302 is a dead pipe pipe section 303;
  • the dead pipeline valve group pipe section 3 further includes a bypass line 304, a manual isolation valve 305 disposed on the bypass line 304, and the bypass line 304 is connected to the waste heat discharge system pipe 2 near the heat pipe section
  • the pipe section of 1 is connected to the dead pipe section 303;
  • the two ends of the bypass line 304 are respectively provided with a first restrictor 306 and a second restrictor 307; the first restrictor 306 and the second restrictor 307 are both 3 mm restrictors;
  • the bypass line 304 has an inner diameter of ⁇ , and the bypass line 304 has a length of 400 ⁇ 1000.
  • the first isolation valve 301 and the second isolation valve 302 are in a closed state, and the manual isolation valve 305 is in a normally open state, so that the pressure of the reactor coolant system communicates with the dead pipe section 303 during normal operation.
  • the pressure in the dead pipe section 303 is increased to the operating pressure of the reactor coolant system (15.5 MPa in the normal operation state), thereby increasing the saturation temperature of the liquid in the dead pipe section 303, effectively avoiding the occurrence of vaporization, and solving the "death" Pipeline "problem.
  • the 3mm restrictor can effectively limit the reactor coolant loss so that it does not threaten the safety of the nuclear power plant.
  • the bypass line 304 is of a suitable length to prevent leakage of the second isolation valve 302, thereby causing the high temperature medium of the reactor coolant system to flow into the residual heat removal system through the bypass line 304.

Abstract

The present invention relates to an inlet pipeline structure of a residual heat removal system capable of avoiding a phenomenon of a "dead pipeline". The structure is arranged between a reactor hot pipe section and a cold pipe section and comprises a residual heat removal system pipe section connected to the hot pipe section and the cold pipe section, and a dead pipeline valve group pipe section arranged on the residual heat removal system pipe section. The dead pipeline valve group pipe section comprises a first isolating valve and a second isolating valve. The first isolating valve and the second isolating valve are connected in series and arranged on a residual heat removal system pipeline. A pipe section of the residual heat removal system pipeline between the first isolating valve and the second isolating valve is a dead pipeline pipe section. The dead pipeline valve group pipe section further comprises a bypass line and a manual isolating valve arranged on the bypass line. One end of the bypass line is connected to a pipe section, close to the hot pipe section, of the residual heat removal system pipeline, and the other end is connected to the dead pipeline pipe section. The present invention can effectively solve the problem of a "dead pipeline", does not threaten the safety of a nuclear power plant, and does not threaten the integrity of the residual heat removal system.

Description

^ ^ 能够避免 "死管道"现象的余热排出***入口管道结构 技术领域  ^ ^ The inlet pipe structure of the waste heat removal system capable of avoiding the "dead pipe" phenomenon
本发明涉及压水堆核电站管道布置领域， 具体涉及一种能够避免 "死管 道"现象的余热排出***入口管道结构。  The invention relates to the field of pipeline arrangement of a pressurized water reactor nuclear power plant, and particularly relates to an inlet pipe structure of a waste heat discharge system capable of avoiding a "dead pipe" phenomenon.
背景技术  Background technique
余热排出***与反应堆冷却剂***相连， 主要用于停堆期间排出堆芯余 热， 是压水堆核电厂重要的辅助***之一。 其入口通过两道隔离阀与反应堆 冷却剂***的主管道热段相连。 核电站正常运行期间， 余热排出***入口处 隔离阀处于关闭状态， 在两道隔离阀之间的管道形成了不流动的低压 "死管 道"。 在现有的核电站设计中， 缺乏一种有效措施提高 "死管道" 内的压力， 反应堆冷却剂***的高温冷却剂通过第一道隔离阀不断加热 "死管道" 内的 液体， 将导致 "死管道" 内液体温度超过其所在压力下对应的饱和温度， 产 生局部沸腾， 杂质在水 /汽界面处聚集， 对阀门闸板造成严重的腐蚀， 影响阀 门的密封性。 这一现象被称为 "死管道"现象， 严重威胁核电厂的安全。  The residual heat removal system is connected to the reactor coolant system and is mainly used to discharge the residual heat of the core during shutdown. It is one of the important auxiliary systems for the pressurized water reactor nuclear power plant. The inlet is connected to the main pipe hot section of the reactor coolant system via two isolation valves. During normal operation of the nuclear power plant, the isolation valve at the inlet of the residual heat removal system is closed, and the pipeline between the two isolation valves forms a low-pressure "dead pipe" that does not flow. In the existing nuclear power plant design, there is a lack of effective measures to increase the pressure in the "dead pipe". The high temperature coolant of the reactor coolant system continuously heats the liquid in the "dead pipe" through the first isolation valve, which will result in "death." The internal liquid temperature of the pipeline exceeds the corresponding saturation temperature at the pressure at which it is located, causing partial boiling. The impurities accumulate at the water/vapor interface, causing serious corrosion to the valve gate and affecting the sealing of the valve. This phenomenon is known as the "dead pipeline" phenomenon, which seriously threatens the safety of nuclear power plants.
发明内容  Summary of the invention
本发明的要解决的技术问题是提供一种提高 "死管道" 内的压力， 以及 "死管道" 内冷却剂的饱和温度， 从而避免 "死管道" 内冷却剂受热汽化， 解决 "死管道" 问题， 同时不会由于这样的布置方式额外增加核电厂运行期 间风险的管道布置结构。  The technical problem to be solved by the present invention is to provide an increase in the pressure in the "dead pipe" and the saturation temperature of the coolant in the "dead pipe", thereby avoiding the vaporization of the coolant in the "dead pipe" and solving the "dead pipe". The problem, at the same time, will not increase the pipeline layout structure during the operation of the nuclear power plant due to such an arrangement.
为了解决上述技术问题， 本发明的技术方案为， 一种能够避免 "死管道" 现象的余热排出***入口管道结构， 其设置在反应堆热管段和冷管段之间， 包括连接所述热管段和冷管段的余热排出***管段、 设置在所述余热排出系 统管段上的死管道阀门组管段； In order to solve the above technical problem, the technical solution of the present invention is an inlet pipe structure of a waste heat discharge system capable of avoiding a "dead pipe" phenomenon, which is disposed between a reactor heat pipe section and a cold pipe section. The invention comprises a waste heat discharge system pipe section connecting the heat pipe section and the cold pipe section, and a dead pipeline valve group pipe section disposed on the waste heat discharge system pipe section;
所述死管道阀门组管段包括第一隔离阀和第二隔离阀， 所述第一隔离阀 和第二隔离阀串连设置在余热排出***管道上； 所述第一隔离阀和第二隔离 阀之间的余热排出***管道的管段为死管道管段；  The dead pipeline valve group pipe section includes a first isolation valve and a second isolation valve, wherein the first isolation valve and the second isolation valve are arranged in series on a waste heat removal system pipe; the first isolation valve and the second isolation valve The pipe section between the waste heat exhaust system piping is a dead pipe section;
所述死管道阀门组管段还包括旁通管线、 设置在所述旁通管线上的手动 隔离阀， 所述旁通管线一端连接到所述余热排出***管道靠近热管段的管段 上， 另一端连接到所述死管道管段上。  The dead pipeline valve group pipe section further includes a bypass line, a manual isolation valve disposed on the bypass line, and one end of the bypass line is connected to the pipe section of the waste heat discharge system pipe near the heat pipe section, and the other end is connected Go to the dead pipe section.
所述旁通管线的两端分别设置有第一限流器和第二限流器。  Two ends of the bypass line are respectively provided with a first restrictor and a second restrictor.
所述第一限流器和第二限流器均为 3mm的限流器。  The first restrictor and the second restrictor are both 3 mm restrictors.
所述旁通管线的内径为 Φ， 所述旁通管线 304的长度为 400〜1000 Φ。 还包括设置在余热排出***管段上的余热排出泵和余热排出热交换器； 所述死管道阀门组管段、 余热排出泵和余热排出热交换器自热管段向冷管段 方向依次布置。  The bypass line has an inner diameter of Φ, and the bypass line 304 has a length of 400 to 1000 Φ. The utility model further comprises a waste heat discharge pump and a waste heat discharge heat exchanger disposed on the pipe section of the waste heat discharge system; the dead pipe valve group pipe section, the residual heat discharge pump and the waste heat discharge heat exchanger are arranged in order from the heat pipe section to the cold pipe section.
反应堆正常运行时， 所述第一隔离阀和第二隔离阀处于关闭状态， 所述 手动隔离阀处于开启状态。  When the reactor is in normal operation, the first isolation valve and the second isolation valve are in a closed state, and the manual isolation valve is in an open state.
本发明的有益效果：  The beneficial effects of the invention:
( 1 )本发明可以将 "死管道"内的压力提高到反应堆冷却剂***的运行 压力， 提高 "死管道" 内液体的饱和温度， 避免汽化现象的出现， 解决 "死 管道" 问题；  (1) The invention can increase the pressure in the "dead pipeline" to the operating pressure of the reactor coolant system, increase the saturation temperature of the liquid in the "dead pipeline", avoid the appearance of vaporization, and solve the "dead pipeline" problem;
(2)本发明可以有效地限值由于旁通管道破裂或第二道隔离阀发生泄漏 引起的反应堆冷却剂水装量的损失， 使其不会威胁到核电厂的安全； (3 )本发明能够有效地限值由于第二道隔离阀发生泄漏而流入余热排出 ***的冷却剂温度， 不会威胁到余热排出***的完整性。 (2) The present invention can effectively limit the loss of the reactor coolant water volume caused by the bypass pipe rupture or the leakage of the second isolation valve, so that it does not threaten the safety of the nuclear power plant; (3) The present invention can effectively limit the temperature of the coolant flowing into the residual heat discharge system due to the leakage of the second isolation valve without impairing the integrity of the waste heat removal system.
國綱  National program
图 1为本发明能够避免 "死管道"现象的余热排出***入口管道结构示 意图；  1 is a schematic view showing the structure of an inlet pipe of a waste heat removal system capable of avoiding a "dead pipe" phenomenon;
图 2为图 1中虚线框图放大示意图。  Figure 2 is an enlarged schematic view of the broken line block diagram of Figure 1.
图中： 1-热管段， 2-余热排出***管道， 3-死管道阀门组管段， 4-余热排 出泵， 5-余热排出热交换器， 6-冷管段， 301-第一隔离阀， 302-第二隔离阀， 303-死管道管段， 304-旁通管线， 305-手动隔离阀， 306-第一限流器， 307-第 二限流器。 以下结合附图和实施例对本发明做进一歩描述。  In the figure: 1- heat pipe section, 2- residual heat discharge system pipe, 3- dead pipe valve group pipe section, 4- residual heat discharge pump, 5- residual heat discharge heat exchanger, 6-cold pipe section, 301-first isolation valve, 302 - Second isolation valve, 303 - dead pipe section, 304 - bypass line, 305 - manual isolation valve, 306 - first restrictor, 307 - second restrictor. The present invention will be further described below in conjunction with the drawings and embodiments.
如图 1所示， 核电站反应堆包括一回路***， 所述一回路***包括若干 个环路， 一般为 2个或 3个环路； 每个环路均包括热管段 1和冷管段 6; 冷 却剂通过泵由冷管段 6进入压力容器并从堆芯吸取热量， 吸取热量后的冷却 剂离开压力容器由热管段 1经过蒸汽发生器释放热量， 释放热量后的冷却剂 回到冷管段 6进而再次进入压力容器从而实现循环； 在所述环路的热管段 1 和冷管段 6之间设置有余热排除***， 包括连接所述热管段 1和所述冷管段 6的余热排出***管道 2、自热管段 1向冷管段 6方向依次设置的死管道阀门 组管段 3、 余热排出泵 4和余热排出热交换器 5;  As shown in FIG. 1, the nuclear power plant reactor includes a primary circuit system including a plurality of loops, generally two or three loops; each loop includes a heat pipe section 1 and a cold pipe section 6; The pump enters the pressure vessel from the cold pipe section 6 and draws heat from the core. The coolant after the heat is removed from the pressure vessel, the heat is released from the heat pipe section 1 through the steam generator, and the heat released by the coolant returns to the cold pipe section 6 and then enters again. The pressure vessel is thereby circulated; a waste heat removal system is disposed between the heat pipe section 1 and the cold pipe section 6 of the loop, including a waste heat discharge system pipe 2 connecting the heat pipe section 1 and the cold pipe section 6, and an automatic heat pipe section 1 a dead pipeline valve group pipe section 3, a residual heat discharge pump 4 and a residual heat discharge heat exchanger 5 arranged in the direction of the cold pipe section 6;
所述死管道阀门组管段 3包括第一隔离阀 301和第二隔离阀 302， 所述 第一隔离阀 301和第二隔离阀 302串连设置在余热排出***管道 2上； 所述 第一隔离阀 301和第二隔离阀 302之间的余热排出***管道 2的管段为死管 道管段 303 ; The dead pipeline valve group pipe section 3 includes a first isolation valve 301 and a second isolation valve 302, and the first isolation valve 301 and the second isolation valve 302 are arranged in series on the waste heat removal system pipe 2; The pipe section of the residual heat discharge system pipe 2 between the first isolation valve 301 and the second isolation valve 302 is a dead pipe pipe section 303;
所述死管道阀门组管段 3还包括旁通管线 304、设置在所述旁通管线 304 上的手动隔离阀 305，所述旁通管线 304—端连接到所述余热排出***管道 2 靠近热管段 1的管段上， 另一端连接到所述死管道管段 303上；  The dead pipeline valve group pipe section 3 further includes a bypass line 304, a manual isolation valve 305 disposed on the bypass line 304, and the bypass line 304 is connected to the waste heat discharge system pipe 2 near the heat pipe section The pipe section of 1 is connected to the dead pipe section 303;
所述旁通管线 304的两端分别设置有第一限流器 306和第二限流器 307; 所述第一限流器 306和第二限流器 307均为 3mm的限流器；  The two ends of the bypass line 304 are respectively provided with a first restrictor 306 and a second restrictor 307; the first restrictor 306 and the second restrictor 307 are both 3 mm restrictors;
所述旁通管线 304的内径为 Φ，所述旁通管线 304的长度为 400 Φ〜 1000 The bypass line 304 has an inner diameter of Φ, and the bypass line 304 has a length of 400 Φ~1000.
Φ ; Φ ;
反应堆正常运行时， 所述第一隔离阀 301和第二隔离阀 302处于关闭状 态， 所述手动隔离阀 305处于常开状态， 使正常运行期间反应堆冷却剂*** 的压力与死管道管段 303内相通， 将死管道管段 303内的压力提高到反应堆 冷却剂***运行压力 （正常运行状态下为 15.5MPa) ， 从而提高死管道管段 303内液体的饱和温度， 有效避免汽化现象的发生， 解决了 "死管道"问题。  When the reactor is in normal operation, the first isolation valve 301 and the second isolation valve 302 are in a closed state, and the manual isolation valve 305 is in a normally open state, so that the pressure of the reactor coolant system communicates with the dead pipe section 303 during normal operation. The pressure in the dead pipe section 303 is increased to the operating pressure of the reactor coolant system (15.5 MPa in the normal operation state), thereby increasing the saturation temperature of the liquid in the dead pipe section 303, effectively avoiding the occurrence of vaporization, and solving the "death" Pipeline "problem.
在旁通管线 304发生破裂导致液体外泄的情况下， 3mm的限流器能够有 效限制反应堆冷却剂的损失， 使其不会威胁到核电厂的安全。  In the event that the bypass line 304 ruptures and the liquid leaks out, the 3mm restrictor can effectively limit the reactor coolant loss so that it does not threaten the safety of the nuclear power plant.
旁通管线 304采用适当的长度可以避免第二隔离阀 302发生泄漏， 从而 导致反应堆冷却剂***的高温介质通过旁通管线 304流入余热排出***。  The bypass line 304 is of a suitable length to prevent leakage of the second isolation valve 302, thereby causing the high temperature medium of the reactor coolant system to flow into the residual heat removal system through the bypass line 304.

Claims

^ ^ ^ ^
1、 一种能够避免 "死管道"现象的余热排出***入口管道结构， 其设 置在反应堆热管段和冷管段之间， 其特征在于： 包括连接所述热管段和冷管 段的余热排出***管段、 设置在所述余热排出***管段上的死管道阀门组管 所述死管道阀门组管段包括第一隔离阀和第二隔离阀， 所述第一隔离阀 和第二隔离阀串连设置在余热排出***管道上； 所述第一隔离阀和第二 阀之间的余热排出***管道的管段为死管道管段； 1. A waste heat discharge system inlet pipe structure that can avoid the "dead pipe" phenomenon, which is arranged between the reactor hot pipe section and the cold pipe section, and is characterized by: including a waste heat discharge system pipe section connecting the hot pipe section and the cold pipe section, The dead pipe valve group pipe is arranged on the pipe section of the waste heat discharge system. The dead pipe valve group pipe section includes a first isolation valve and a second isolation valve. The first isolation valve and the second isolation valve are arranged in series on the waste heat discharge system. On the system pipeline; The section of the waste heat discharge system pipeline between the first isolation valve and the second valve is a dead pipeline section;
所述死管道阀门组管段还包括旁通管线、 设置在所述旁通管线上的手动 隔离阀， 所述旁通管线一端连接到所述余热排出***管道靠近热管段的管段 上， 另一端连接到所述死管道管段上。 The dead pipe valve group pipe section also includes a bypass pipeline and a manual isolation valve provided on the bypass pipeline. One end of the bypass pipeline is connected to the pipe section of the waste heat discharge system pipe close to the heat pipe section, and the other end is connected to onto the dead pipe segment.
2、按照权利要求 1所述的管道结构， 其特征在于： 所述旁通管线的两端 分别设置有第一限流器和第二限流器。 2. The pipeline structure according to claim 1, characterized in that: a first flow restrictor and a second flow restrictor are respectively provided at both ends of the bypass pipeline.
3、按照权利要求 2所述的管道结构， 其特征在于： 所述第一限流器和第 二限流器均为 3mm的限流器。 3. The pipeline structure according to claim 2, characterized in that: the first flow limiter and the second flow limiter are both 3mm flow limiters.
4、按照权利要求 1所述的管道结构， 其特征在于： 所述旁通管线的内径 为 Φ， 所述旁通管线的长度为 400 Φ〜1000 Φ。 4. The pipeline structure according to claim 1, characterized in that: the inner diameter of the bypass pipeline is Φ, and the length of the bypass pipeline is 400 Φ~1000 Φ.
5、 按照权利要求 1所述的管道结构， 其特征在于： 还包括设置在余热 排出***管段上的余热排出泵和余热排出热交换器;所述死管道阀门组管段、 余热排出泵和余热排出热交换器自热管段向冷管段方向依次布置。 5. The pipeline structure according to claim 1, characterized in that: it also includes a waste heat discharge pump and a waste heat discharge heat exchanger arranged on the waste heat discharge system pipe section; the dead pipe valve group pipe section, the waste heat discharge pump and the waste heat discharge The heat exchangers are arranged sequentially from the heating pipe section to the cold pipe section.
6、 按照权利要求 1所述的管道结构， 其特征在于： 反应堆正常运行时， 所述第一隔离阀和第二隔离阀处于关闭状态，所述手动隔离阀处于开启状态。 6. The pipeline structure according to claim 1, characterized in that: when the reactor is operating normally, the first isolation valve and the second isolation valve are in a closed state, and the manual isolation valve is in an open state.
PCT/CN2013/088412 2012-12-10 2013-12-03 Inlet pipeline structure of residual heat removal system capable of avoiding phenomenon of "dead pipeline" WO2014090100A1 (en)

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