WO2015014047A1 - 核电站热段安全注入系统 - Google Patents

核电站热段安全注入系统 Download PDF

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Publication number
WO2015014047A1
WO2015014047A1 PCT/CN2013/087741 CN2013087741W WO2015014047A1 WO 2015014047 A1 WO2015014047 A1 WO 2015014047A1 CN 2013087741 W CN2013087741 W CN 2013087741W WO 2015014047 A1 WO2015014047 A1 WO 2015014047A1
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WIPO (PCT)
Prior art keywords
hot section
safety injection
electric isolation
isolation valve
hot
Prior art date
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Ceased
Application number
PCT/CN2013/087741
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English (en)
French (fr)
Inventor
咸春宇
温亮
李盛杰
唐辉
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
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Application filed by China General Nuclear Power Corp, China Nuclear Power Engineering Co Ltd filed Critical China General Nuclear Power Corp
Priority to GB1513533.8A priority Critical patent/GB2524453B/en
Publication of WO2015014047A1 publication Critical patent/WO2015014047A1/zh
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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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 belongs to the field of nuclear power safety, and more particularly to a safety injection system for a thermal section of a nuclear power plant capable of improving the probability of successful safety injection of a hot section under accident conditions.
  • the RIS system safety injection system
  • the RHR system main heat removal system
  • the hot section injection pipeline of the RIS system and the hot section water intake pipeline of the RHR system are combined into one, so there is no need to install a separate RHR system, thus saving equipment and improving the economic efficiency of the nuclear power plant. the goal of.
  • the above RIS system isolates the thermal circuit of the RIS system from the primary circuit of the reactor coolant system through two electric isolation valves located on the combined pipeline; in normal shutdown conditions, when the primary circuit When the pressure and temperature are reduced to the access conditions of the RHR system, the residual heat is discharged under the shutdown condition by opening two electric isolation valves; in the accident condition, when the hot section safety injection function needs to be performed, the operation is required.
  • Two electric isolation valves are opened in the main control room to ensure that the boron-containing water can be injected from the hot section. In other words, whether the electric isolation valve can be successfully opened determines whether the hot section safety injection can be successful.
  • the object of the present invention is to provide a safety injection system for a thermal power station of a nuclear power plant capable of improving the probability of successful safety injection in a hot section under accident conditions.
  • the present invention provides a nuclear power plant hot section safety injection system comprising a hot section connecting pipe with two electric isolation valves spaced apart, and a heat section safety section provided with at least one check valve Injecting the pipe, the two ends of the hot section safety injection pipe are respectively connected to the hot section connecting pipe so that the check valve thereon is connected in parallel with at least one of the two electric isolation valves of the hot segment connecting pipe.
  • one end of the hot section connecting pipe is connected to a low pressure safety injection pipe, and the other end is connected to a hot section of the first circuit of the reactor coolant system;
  • the valves are a first electric isolation valve adjacent to the low pressure safety injection conduit and a second electric isolation valve adjacent to the hot section of the primary coolant of the reactor coolant system.
  • two check valves are connected in parallel with the first electric isolation valve and the second electric isolation valve.
  • one end of the hot section safety injection pipe is connected at a position where the hot section connection pipe is located between the low pressure safety injection pipe and the first electric isolation valve, and the other end is connected to the heat.
  • the segment connecting pipe is located between the second electric isolation valve and the first circuit hot section of the reactor coolant system, so that the two check valves are simultaneously connected in parallel with the first electric isolation valve and the second electric isolation valve.
  • the hot section safety injection pipe is provided with a check valve in parallel with the first electric isolation valve.
  • one end of the hot section safety injection pipe is connected to the position of the hot section connecting pipe between the low pressure safety injection pipe and the first electric isolation valve. And the other end is connected at a position where the hot section connecting pipe is located between the first electric isolation valve and the second electric isolation valve, so that the check valve is connected in parallel with the first electric isolation valve.
  • the hot section safety injection pipe is provided with a check valve in parallel with the second electric isolation valve.
  • one end of the hot section safety injection pipe is connected to the hot section connecting pipe at a position between the first electric isolation valve and the second electric isolation valve, and the other end is connected.
  • the position on the hot section connecting pipe is between the second electric isolation valve and the hot section of the first circuit of the reactor coolant system, so that the check valve is connected in parallel with the second electric isolation valve.
  • the present invention separates the water intake function of the RHR hot section from the hot water injection function by setting a separate hot section safety injection pipeline; and injects the pipeline safely in a separate heat section.
  • the check valve is arranged to realize the isolation from the primary circuit of the reactor coolant system under normal operating conditions. Since the check valve does not require manual operation by the operator after the accident, it is not necessary to configure the electrical system as the power source. The maintenance and maintenance costs are low, and the probability of safe injection success of the hot section after the accident is greatly improved, and the CDF (Core Damage Frequency) and the LRF value (Large Release Frequency) are effectively reduced.
  • CDF Core Damage Frequency
  • LRF value Large Release Frequency
  • FIG. 1 is a schematic structural view of a first embodiment of a thermal injection safety injection system for a nuclear power plant according to the present invention.
  • 2 is a schematic structural view of a second embodiment of a safety injection system for a thermal section of a nuclear power plant according to the present invention.
  • 3 is a schematic structural view of a third embodiment of a thermal injection safety injection system for a nuclear power plant according to the present invention.
  • a nuclear power plant hot section safety injection system 100 includes a hot section connecting duct 10 and a hot section safety injection duct 20, and one end of the hot section connecting duct 10 is connected to a low voltage.
  • the safe injection conduit 30 is connected to the hot section 44 of the primary coolant circuit 40 of the reactor coolant system.
  • the reactor coolant system primary circuit 40 includes a reactor core 41, a steam generator 42, a main pump 43, a heat section 44, a cold section 45, and a transition section 46, wherein the heat section 44 is coupled to the reactor core 41 and the steam generator 42. Between the cold section 45 is connected between the reactor core 41 and the main pump 43, and the transition section 46 is connected between the main pump 43 and the steam generator 42.
  • the first electric isolation valve 101 and the second electric isolation valve 102 are spaced apart from each other in the hot section connecting pipe 10. In the position, the first electric isolation valve 101 is adjacent to the low pressure safety injection pipe 30, and the second electric isolation valve 102 is close to the reactor coolant.
  • the hot section 44 of the primary circuit 40 of the system is close to the reactor coolant.
  • the two ends of the hot section safety injection pipe 20 are respectively connected to the hot section connection pipe 10, and two check valves 201, 202 are provided thereon.
  • one end of the hot section safety injection pipe 20 is connected at a position where the hot section connection pipe 10 is located between the low pressure safety injection pipe 30 and the first electric isolation valve 101, and the other end is connected to the hot section connection pipe 10 at the second electric isolation.
  • the position between the valve 102 and the hot section 44 of the primary coolant circuit 40 of the reactor coolant system is such that the two check valves 201, 202 are simultaneously connected in parallel with the first electrically isolated valve 101 and the second electrically isolated valve 102.
  • the present invention separates the RHR hot section water intake function from the hot section water injection function by providing a separate hot section safety injection pipe 20, so that the two do not affect each other; and by setting two stops on the separate hot section safety injection pipe 20.
  • the return valves 201, 202 are used to isolate the primary coolant circuit 40 from the reactor coolant system under normal operating conditions. Since the two check valves 201, 202 do not require manual operation by the operator after an accident, there is no need to configure the electrical system as a power source. The source not only has the low cost of configuration, maintenance and overhaul, but also greatly increases the probability of successful safety injection of the hot section after the accident, effectively reducing the CDF and LRF values.
  • a nuclear power plant hot section safety injection system 200 includes a hot section connecting duct 10 and a hot section safe injection duct 50, wherein the hot section connecting duct 10 One end is connected to a low pressure safety injection line 30 and the other end is connected to a hot section 44 of the reactor coolant system primary circuit 40.
  • the hot section connection conduit 10 is spaced apart from a first electrically isolated valve 101 adjacent the low pressure safety injection conduit 30 and a second electrically isolated valve 102 adjacent the hot section 44 of the primary coolant 40 of the reactor coolant system.
  • Both ends of the hot section safety injection pipe 50 are connected to the hot section connection pipe 10, respectively, and a check valve 501 is provided thereon.
  • one end of the hot section safety injection pipe 50 is connected at a position where the hot section connection pipe 10 is located between the low pressure safety injection pipe 30 and the first electric isolation valve 101, and the other end is connected to the hot section connection pipe 10 at the first electric isolation.
  • the position between the valve 101 and the second electric isolation valve 102 is such that the check valve 501 is connected in parallel with the first electric isolation valve 101.
  • the operator when the hot spot injection function needs to be performed under the medium and large LOCA accident conditions, the operator does not need to manually open the first and second electric isolation valves 101 and 102 at the same time, but only needs to manually open the second electric motor.
  • the isolation valve 102 is sufficient, so that the probability of successful injection of the hot section after the accident is also significantly improved.
  • a nuclear power plant hot section safety injection system 300 includes a hot section connecting duct 10 and a hot section safe injection duct 60, wherein one end of the hot section connecting duct 10 is connected to a low voltage.
  • the safety injection conduit 30 is connected to the hot section 44 of the primary coolant circuit 40 of the reactor coolant system.
  • the hot section connection pipe 10 is spaced apart from the first electric isolation valve 101 adjacent to the low pressure safety injection line 30 and the second electric isolation valve 102 adjacent to the hot section 44 of the primary coolant circuit 40 of the reactor coolant system.
  • the two ends of the hot section safety injection pipe 60 are respectively connected to the hot section connection pipe 10, and a check valve 601 is provided thereon.
  • one end of the hot section safety injection pipe 60 is connected to the hot section connecting pipe 10 at a position between the first electric isolation valve 101 and the second electric isolation valve 102, and the other end is connected to the hot section connecting pipe 10 at the
  • the position between the second electrically isolated valve 102 and the hot section 44 of the primary coolant circuit 40 of the reactor coolant system causes the check valve 601 to be in parallel with the second electrically isolated valve 102.
  • the hot zone injection function needs to be performed under the medium and large LOCA accident conditions, It is not necessary for the operator to manually open the first and second electric isolation valves 101, 102 at the same time, but only the first electric isolation valve 101 needs to be manually opened, so that the probability of successful safety injection of the hot section after the accident is also significantly improved.
  • the present invention can also be appropriately modified and modified as described above. Therefore, the present invention is not limited to the specific embodiments disclosed and described herein, and modifications and variations of the present invention are intended to fall within the scope of the appended claims.
  • the present invention is not limited to the specific embodiments disclosed and described herein, and modifications and variations of the present invention are intended to fall within the scope of the appended claims.
  • some specific terms are used in the specification, these terms are merely for convenience of description and do not impose any limitation on the invention.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

一种核电站热段安全注入系统（100，200，300），包括一条间隔设有两个电动隔离阀（101，102）的热段连接管道（10）和一条设有至少一个止回阀（201，202，501，601）的热段安全注入管道（20，50，60），热段安全注入管道（20，50，60）的两端分别连接至热段连接管道（10）而使其上的止回阀（201，202，501，601）与热段连接管道（10）的两个电动隔离阀（101，102）中的至少一个相并联。该安全注入系统（100，200，300）配置简单、维护及检修成本低，而且提高了事故后热段安全注入成功概率，有效地降低了CDF和LRF值。

Description

核电站热段安全注入系统 技术领域
本发明属于核电安全领域， 更具体地说， 本发明涉及一种能在事故工况下 提高热段安全注入成功概率的核电站热段安全注入系统。 背景技术
在一种普遍采用的机组设计中， 将 RIS系统 (安全注入系统)与 RHR系统 (余 热排出系统)进行了合并， RIS系统以 RHR系统模式运行并带走正常和事故工况 下堆芯的余热。 RIS系统与 RHR系统进行合并后， RIS系统的热段注入管道和 RHR系统的热段取水管道合二为一，也就无需再设置单独的 RHR系统， 因此实 现了节省设备、 提高核电厂经济性的目的。
在核电站以正常功率运行期间， 上述 RIS 系统通过设于合并管道上的两个 电动隔离阀来实现 RIS 系统与反应堆冷却剂系统一回路热段的隔离； 在正常停 堆工况下， 当一回路的压力和温度降低到 RHR系统的接入条件时， 通过开启两 个电动隔离阀执行停堆工况下的余热排出； 在事故工况下， 当需要执行热段安 全注入功能时， 则需要操作员在主控室打开两个电动隔离阀， 以确保含硼水可 以从热段注入。 也就是说， 电动隔离阀是否能够成功开启， 决定了热段安全注 入能否成功。
RIS系统和 RHR系统的合并虽然因不需要设置单独的 RHR系统而实现了节 省设备、 提高核电站经济性的目的， 但同时也因为存在以下问题而增大了热段 安全注入失效的概率： 1)在执行热段安全注入功能时， 需要操作员手动开启两个 RCPB隔离阀， 由于事故后安全壳内的环境恶劣， 阀门拒开的风险较大； 2)两个 RCPB隔离阀都为电动隔离阀， 因此电气系统的故障也会导致隔离阀拒开， 增大 了热段安全注入失效的概率。 有鉴于此， 确有必要提供一种能提高事故后热段安全注入成功概率的核电 站热段安全注入系统。 发明内容
本发明的目的在于： 提供一种能在事故工况下提高热段安全注入成功概率 的核电站热段安全注入系统。
为了实现上述发明目的， 本发明提供了一种核电站热段安全注入系统， 其 包括一条间隔设有两个电动隔离阀的热段连接管道， 还包括一条设有至少一个 止回阀的热段安全注入管道， 所述热段安全注入管道的两端分别连接至热段连 接管道而使其上的止回阀与热段连接管道的两个电动隔离阀中的至少一个相并 联。
作为本发明核电站热段安全注入系统的一种改进， 所述热段连接管道的一 端连接至一条低压安全注入管道、 另一端连接至反应堆冷却剂系统一回路的热 段； 所述两个电动隔离阀分别为靠近低压安全注入管道的第一电动隔离阀及靠 近反应堆冷却剂系统一回路热段的第二电动隔离阀。
作为本发明核电站热段安全注入系统的一种改进， 所述热段安全注入管道 上间隔设有两个与第一电动隔离阀及第二电动隔离阀相并联的止回阀。
作为本发明核电站热段安全注入系统的一种改进， 所述热段安全注入管道 的一端连接在热段连接管道位于低压安全注入管道与第一电动隔离阀之间的位 置， 另一端连接在热段连接管道位于第二电动隔离阀与反应堆冷却剂系统一回 路热段之间的位置， 从而使得两个止回阀与第一电动隔离阀及第二电动隔离阀 同时并联。
作为本发明核电站热段安全注入系统的一种改进， 所述热段安全注入管道 上设有一个与第一电动隔离阀相并联的止回阀。
作为本发明核电站热段安全注入系统的一种改进， 所述热段安全注入管道 的一端连接在热段连接管道位于低压安全注入管道与第一电动隔离阀之间的位 置， 另一端连接在热段连接管道位于第一电动隔离阀和第二电动隔离阀之间的 位置， 从而使得所述止回阀与第一电动隔离阀相并联。
作为本发明核电站热段安全注入系统的一种改进， 所述热段安全注入管道 上设置有一个与第二电动隔离阀并联的止回阀。
作为本发明核电站热段安全注入系统的一种改进， 所述热段安全注入管道 的一端连接在热段连接管道上位于第一电动隔离阀和第二电动隔离阀之间的位 置， 另一端连接在热段连接管道上位于第二电动隔离阀与反应堆冷却剂系统一 回路热段之间的位置， 从而使得止回阀与第二电动隔离阀相并联。
与现有技术相比， 本发明通过设置一条单独的热段安全注入管道， 将 RHR 热段取水功能与热段注水功能分离而使两者互不影响； 又通过在单独的热段安 全注入管道上设置止回阀来实现正常运行工况下与反应堆冷却剂系统一回路的 隔离， 由于止回阀在事故后不需要操作员手动操作， 也不需要配置电气系统作 为动力源， 不仅配置筒单、 维护及检修成本低， 而且大幅提高了事故后热段安 全注入成功概率， 有效地降低了 CDF(Core Damage Frequency, 堆芯损坏频率） 和 LRF值 (Large Release Frequency , 大量放射性释放频率）。 附图说明
下面结合附图和具体实施方式， 对本发明核电站热段安全注入系统进行详 细说明。
图 1为本发明核电站热段安全注入系统的第一实施方式的结构示意图。 图 2为本发明核电站热段安全注入系统的第二实施方式的结构示意图。 图 3为本发明核电站热段安全注入系统的第三实施方式的结构示意图。 具体实施方式
为了使本发明的发明目的、 技术方案及其有益技术效果更加清晰， 以下结 合附图和具体实施方式， 对本发明进行进一步详细说明。 应当理解的是， 本说 明书中描述的具体实施方式仅仅是为了解释本发明， 并非为了限定本发明。 请参阅图 1所示，本发明第一实施方式提供的核电站热段安全注入系统 100, 包括一条热段连接管道 10及一条热段安全注入管道 20, 热段连接管道 10的一 端连接至一条低压安全注入管道 30、 另一端连接至反应堆冷却剂系统一回路 40 的热段 44。
反应堆冷却剂系统一回路 40包括反应堆堆芯 41、 蒸汽发生器 42、 主泵 43、 热段 44、 冷段 45及过渡段 46, 其中， 热段 44连接在反应堆堆芯 41与蒸汽发 生器 42之间， 冷段 45连接在反应堆堆芯 41与主泵 43之间， 过渡段 46连接在 主泵 43与蒸汽发生器 42之间。
热段连接管道 10上间隔设有第一电动隔离阀 101和第二电动隔离阀 102, 在位置上，第一电动隔离阀 101靠近低压安全注入管道 30,第二电动隔离阀 102 靠近反应堆冷却剂系统一回路 40的热段 44。
热段安全注入管道 20的两端分别连接至热段连接管道 10,其上设有两个止 回阀 201、 202。 具体地， 热段安全注入管道 20的一端连接在热段连接管道 10 位于低压安全注入管道 30与第一电动隔离阀 101之间的位置， 另一端连接在热 段连接管道 10位于第二电动隔离阀 102与反应堆冷却剂系统一回路 40的热段 44之间的位置， 从而使得两个止回阀 201、 202与第一电动隔离阀 101及第二电 动隔离阀 102同时并联。
本发明通过提供一条单独的热段安全注入管道 20,将 RHR热段取水功能与 热段注水功能分离而使两者互不影响； 又通过在单独的热段安全注入管道 20上 设置两个止回阀 201、 202来实现正常运行工况下与反应堆冷却剂系统一回路 40 的隔离， 由于两个止回阀 201、 202在事故后不需要操作员手动操作， 也不需要 配置电气系统作为动力源， 不仅配置筒单、 维护及检修成本低， 而且大幅提高 了事故后热段安全注入成功概率， 有效地降低了 CDF和 LRF值。
请参阅图 2, 本发明第二实施方式提供的核电站热段安全注入系统 200, 包 括一条热段连接管道 10及一条热段安全注入管道 50, 其中， 热段连接管道 10 的一端连接至一条低压安全注入管道 30、 另一端连接至反应堆冷却剂系统一回 路 40的热段 44。
热段连接管道 10上间隔设有靠近低压安全注入管道 30的第一电动隔离阀 101及靠近反应堆冷却剂系统一回路 40的热段 44的第二电动隔离阀 102。
热段安全注入管道 50的两端分别连接至热段连接管道 10,其上设有一个止 回阀 501。 具体地， 热段安全注入管道 50的一端连接在热段连接管道 10位于低 压安全注入管道 30与第一电动隔离阀 101之间的位置， 另一端连接在热段连接 管道 10位于第一电动隔离阀 101及第二电动隔离阀 102之间的位置， 从而使得 止回阀 501与第一电动隔离阀 101相并联。
根据本实施方式， 在中、 大 LOCA事故工况下需要执行热段注入功能时， 不需要操作员同时手动开启第一、 第二电动隔离阀 101、 102, 而是仅需手动开 启第二电动隔离阀 102 即可， 因此同样显著提高了事故后热段安全注入成功的 概率。
请参阅图 3, 本发明第三实施方式提供的核电站热段安全注入系统 300, 包 括一条热段连接管道 10及一条热段安全注入管道 60, 其中， 热段连接管道 10 的一端连接至一条低压安全注入管道 30、 另一端连接至反应堆冷却剂系统一回 路 40的热段 44。
热段连接管道 10上间隔设置有靠近低压安全注入管道 30的第一电动隔离 阀 101及靠近反应堆冷却剂系统一回路 40的热段 44的第二电动隔离阀 102。
热段安全注入管道 60的两端分别连接至热段连接管道 10,其上设有一个止 回阀 601。 具体地， 热段安全注入管道 60的一端连接在热段连接管道 10上位于 第一电动隔离阀 101与第二电动隔离阀 102之间的位置， 另一端连接在热段连 接管道 10上位于第二电动隔离阀 102与反应堆冷却剂系统一回路 40的热段 44 之间的位置， 从而使得止回阀 601与第二电动隔离阀 102相并联。
根据本实施方式， 在中、 大 LOCA事故工况下需要执行热段注入功能时， 不需要操作员同时手动开启第一、 第二电动隔离阀 101、 102, 而是仅需手动开 启第一电动隔离阀 101 即可， 因此同样显著提高了事故后热段安全注入成功的 概率。
根据上述原理， 本发明还可以对上述实施方式进行适当的变更和修改。 因 此， 本发明并不局限于上面揭示和描述的具体实施方式， 对本发明的一些修改 和变更也应当落入本发明的权利要求的保护范围内。 此外， 尽管本说明书中使 用了一些特定的术语， 但这些术语只是为了方便说明， 并不对本发明构成任何 限制。

Claims

权 利 要 求 书
1. 一种核电站热段安全注入系统， 包括一条间隔设有两个电动隔离阀的热 段连接管道， 其特征在于： 还包括一条设有至少一个止回阀的热段安全注入管 道， 热段安全注入管道的两端分别连接至热段连接管道而使其上的止回阀与热 段连接管道的两个电动隔离阀中的至少一个相并联。
2. 根据权利要求 1所述的核电站热段安全注入系统， 其特征在于： 所述热 段连接管道的一端连接至一条低压安全注入管道、 另一端连接至反应堆冷却剂 系统一回路的热段； 所述两个电动隔离阀分别为靠近低压安全注入管道的第一 电动隔离阀及靠近反应堆冷却剂系统一回路热段的第二电动隔离阀。
3. 根据权利要求 2所述的核电站热段安全注入系统， 其特征在于： 所述热 段安全注入管道上间隔设有两个与第一电动隔离阀及第二电动隔离阀相并联的 止回阀。
4. 根据权利要求 3所述的核电站热段安全注入系统， 其特征在于： 所述热 段安全注入管道的一端连接在热段连接管道位于低压安全注入管道与第一电动 隔离阀之间的位置， 另一端连接在热段连接管道位于第二电动隔离阀与反应堆 冷却剂系统一回路热段之间的位置， 两个止回阀与第一电动隔离阀及第二电动 隔离阀同时并联。
5. 根据权利要求 2所述的核电站热段安全注入系统， 其特征在于： 所述热 段安全注入管道上设有一个与第一电动隔离阀相并联的止回阀。
6. 根据权利要求 5所述的核电站热段安全注入系统， 其特征在于： 所述热 段安全注入管道的一端连接在热段连接管道位于低压安全注入管道与第一电动 隔离阀之间的位置， 另一端连接在热段连接管道位于第一电动隔离阀和第二电 动隔离阀之间的位置， 所述止回阀与第一电动隔离阀相并联。
7. 根据权利要求 2所述的核电站热段安全注入系统， 其特征在于： 所述热 段安全注入管道上设置有一个与第二电动隔离阀相并联的止回阀。
8. 根据权利要求 7所述的核电站热段安全注入系统， 其特征在于： 所述热 段安全注入管道的一端连接在热段连接管道上位于第一电动隔离阀和第二电动 隔离阀之间的位置， 另一端连接在热段连接管道上位于第二电动隔离阀与反应 堆冷却剂系统一回路热段之间的位置， 止回阀与第二电动隔离阀相并联。
PCT/CN2013/087741 2013-08-01 2013-11-24 核电站热段安全注入系统 Ceased WO2015014047A1 (zh)

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