WO2014090142A1 - 一种压水堆核电厂一回路事故排气系统 - Google Patents

一种压水堆核电厂一回路事故排气系统 Download PDF

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Publication number
WO2014090142A1
WO2014090142A1 PCT/CN2013/089027 CN2013089027W WO2014090142A1 WO 2014090142 A1 WO2014090142 A1 WO 2014090142A1 CN 2013089027 W CN2013089027 W CN 2013089027W WO 2014090142 A1 WO2014090142 A1 WO 2014090142A1
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Prior art keywords
accident
series
power plant
nuclear power
pressurized water
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Application number
PCT/CN2013/089027
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English (en)
French (fr)
Inventor
张玉龙
任云
赖建永
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中国核动力研究设计院
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Application filed by 中国核动力研究设计院 filed Critical 中国核动力研究设计院
Publication of WO2014090142A1 publication Critical patent/WO2014090142A1/zh
Priority to ZA2015/04983A priority Critical patent/ZA201504983B/en

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • 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 an accident response system for a pressurized water reactor nuclear power plant, and particularly relates to a primary circuit accident exhaust system of a pressurized water reactor nuclear power plant.
  • One-circuit accidental exhaust is a serious accident mitigation measure.
  • the accident exhaust system is put into operation, and the non-condensable gas accumulated at the top of the reactor pressure vessel is discharged, thereby preventing the influence of these non-condensable gases on the heat transfer of the reactor core, and ensuring only the only soda in the reactor coolant system. Interface to mitigate the consequences of the accident.
  • the domestic second-generation nuclear power plant only had a normal exhaust system.
  • the reactor coolant system was manually vented only during the start-up process of the power station or before and after refueling, in order to perform relevant water-filling operations on the system.
  • the non-condensable gas inside the reactor pressure vessel cannot be discharged, which affects the heat transfer of the reactor core.
  • the object of the present invention is to provide a primary circuit accident exhaust system of a pressurized water reactor nuclear power plant.
  • a large amount of non-condensable gas is generated in the reactor pressure vessel, and these gases will accumulate on the top of the reactor pressure vessel.
  • the operator manually opens the accidental exhaust gas in the main control room according to the corresponding signal and accident regulations, and discharges the non-condensable gas accumulated at the top of the reactor pressure vessel, thereby preventing the non-condensable gases from being reacted to the reactor.
  • the effect of a core on a primary circuit accident of a pressurized water reactor nuclear power plant ensuring that there is only one vapor-water interface in the reactor coolant system to mitigate the consequences of the accident.
  • the present invention is achieved by a primary circuit accident exhaust system for a pressurized water reactor nuclear power plant comprising an accidental exhaust port connected between a reactor pressure vessel and a normal exhaust gas.
  • the accident exhaust enthalpy is divided into two series, which are taken from the top of the reactor pressure vessel, and through two parallel common relations columns, the first normally closed electromagnetic enthalpy and the second normally closed electromagnetic enthalpy are connected in series to form a series A, The three normally-off electromagnetic ⁇ and the fourth normally-closed electromagnetic ⁇ are connected in series to form a series B, which is connected in parallel to the regulator and the ⁇ discharge line enters the pressure relief box.
  • the invention has the advantages that the system adopts electromagnetic enthalpy, the performance is stable and reliable, and the action is rapid, which can effectively alleviate the serious accident consequences and ensure the integrity of the reactor pressure vessel under severe accidents.
  • FIG. 1 is a schematic diagram of an exhaust system of a primary circuit accident of a pressurized water reactor nuclear power plant according to the present invention.
  • 1 reactor pressure vessel 2 normal exhaust enthalpy, 3 accident exhaust enthalpy, 4 nuclear island exhaust and drainage system, 5 pressure relief tank, 6 first normally closed electromagnetic ⁇ , 7 second normally closed electromagnetic ⁇ , 8 the third normally closed electromagnetic ⁇ , 9 the fourth normally closed electromagnetic ⁇ .
  • a primary circuit accident exhaust system of a pressurized water reactor nuclear power plant comprising an accidental exhaust gas enthalpy 3 connected between the reactor pressure vessel 1 and the normal exhaust gas enthalpy 2 through a pipeline, wherein the accident exhaust enthalpy 3 is divided into two Series, drawn from the top of the reactor pressure vessel, through two parallel common relations, that is, the first normally closed electromagnetic ⁇ 6 and the second normally closed electromagnetic ⁇ 7 are connected in series to form series A, the third normally closed electromagnetic ⁇ 8 and The fourth normally closed electromagnetic ⁇ 9 is connected in series to form series B, and then connected in parallel to the regulator's safety sputum discharge line, and finally enters the pressure relief tank 5.
  • the accident exhaust system When the unit is in normal operation, the accident exhaust system is in standby and the accident exhaust is closed. Under accident conditions, a large amount of non-condensable gas is generated in the reactor pressure vessel, which accumulates on top of the reactor pressure vessel and affects the heat transfer of the reactor core.
  • the operator manually opens two series of accidental exhaust gases in the main control room according to the corresponding signal and accident regulations, and discharges the non-condensable gas accumulated on the top of the reactor pressure vessel to the reactor pressure. Container, to alleviate the consequences of the accident.

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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

一种压水堆核电厂一回路事故排气系统，属于压水堆核电厂的事故应对系统，包括连接在反应堆压力容器（1）与正常排气阀（2）之间的事故排气阀（3）。所述的事故排气阀（3）分为两个并联系列，从反应堆压力容器顶部引出，每个系列由两个常关电磁阀串联构成，两个系列并联接入稳压器安全阀排放管线进入卸压箱。该系统采取电磁阀，性能稳定可靠，动作迅速，可以有效地缓解严重事故后果，确保严重事故下反应堆压力容器的完整性。

Description

一种压水堆核电厂一回路事故排气系统
技术领域
本发明属于一种压水堆核电厂的事故应对系统， 具体涉及一种压水堆核 电厂一回路事故排气系统。
背景技术
一回路事故排气是一种严重事故缓解措施。 在事故工况下， 事故排气系 统投入运行， 排出反应堆压力容器顶部积聚的不可凝气体， 从而防止这些非 凝结性气体对反应堆堆芯传热的影响， 保证反应堆冷却剂系统中只有唯一的 汽水界面， 缓解事故后果。
以往国内二代加核电站仅有正常排气系统，仅在电站启动过程或换料前、 后， 手动对反应堆冷却剂系统排气， 以便对系统进行有关的充水操作。 在事 故工况下， 无法排出反应堆压力容器里面的不可凝结的气体， 影响反应堆堆 芯的传热。
发明内容
本发明的目的是提供一种压水堆核电厂一回路事故排气系统， 在事故工 况下， 反应堆压力容器内会产生大量的不凝结性气体， 这些气体会积聚在反 应堆压力容器顶部， 当需要排出这些不凝结性气体时， 由操纵员根据相应的 信号和事故规程在主控制室手动开启事故排气闽， 排出反应堆压力容器顶部 积聚的不可凝气体， 从而防止这些非凝结性气体对反应堆堆芯一种压水堆核 电厂一回路事故排气方法的影响， 保证反应堆冷却剂系统中只有唯一的汽水 界面， 缓解事故后果。 本发明是这样实现的， 一种压水堆核电厂一回路事故排气系统， 它包括 连接在反应堆压力容器与正常排气闽之间的事故排气闽。 所述的事故排气闽分为两个系列， 从反应堆压力容器顶部引出， 经两个 并联的常关系列， 第一个常关电磁闽与第二个常关电磁闽串联构成系列 A， 第三个常关电磁闽与第四个常关电磁闽串联构成系列 B， 并联接入稳压器安 全闽排放管线进入卸压箱。 本发明的优点是， 该系统采取电磁闽， 性能稳定可靠， 动作迅速， 可以 有效地缓解严重事故后果， 确保严重事故下反应堆压力容器的完整性。
附图说明 图 1为本发明所提供的一种压水堆核电厂一回路事故排气系统示意图。 图中， 1反应堆压力容器， 2正常排气闽， 3事故排气闽， 4核岛排气和 疏水系统， 5卸压箱， 6第一个常关电磁闽， 7第二个常关电磁闽， 8第三个 常关电磁闽， 9第四个常关电磁闽。
具体实施方式 下面结合附图和实施例对本发明进行详细介绍： "压水堆核电厂一回路事故排气系统"在发生事故时，通过开启事故排 气闽， 将积聚在反应堆压力容器顶部的不凝结性气体排出反应堆压力容器， 缓解事故后果。 一种压水堆核电厂一回路事故排气系统， 它包括通过管路连接在反应堆 压力容器 1与正常排气闽 2之间的事故排气闽 3， 其中事故排气闽 3分为两 个系列， 从反应堆压力容器顶部引出， 经两个并联的常关系列， 即第一个常 关电磁闽 6与第二个常关电磁闽 7串联构成系列 A， 第三个常关电磁闽 8与 第四个常关电磁闽 9串联构成系列 B，之后并联接入稳压器安全闽排放管线， 最后进入卸压箱 5。
事故排气闽： 反应堆正常运行时， 该闽门关闭， 为一回路边界的隔离闽； 事故时， 打开该闽门， 排出反应堆压力容器顶部的不可凝气体。
在机组正常运行时， 事故排气系统备用， 事故排气闽处于关闭状态。 在 事故工况下， 反应堆压力容器内会产生大量的不凝结性气体， 这些气体会积 聚在反应堆压力容器顶部， 影响反应堆堆芯的传热。
当需要排出这些不凝结性气体时， 由操纵员根据相应的信号和事故规程 在主控制室手动开启两个系列的事故排气闽， 将积聚在反应堆压力容器顶部 的不凝结性气体排出反应堆压力容器， 缓解事故后果。

Claims

& 禾 J 要
1、一种压水堆核电厂一回路事故排气系统， 其特征在于： 它包括连接在 反应堆压力容器 （1) 与正常排气闽 (2) 之间的事故排气闽 (3) 。
2、如权利要求 1所述的一种压水堆核电厂一回路事故排气系统，其特征 在于： 所述的事故排气闽 (3) 分为两个系列， 从反应堆压力容器顶部引出， 经两个并联的常关系列， 第一个常关电磁闽 (6) 与第二个常关电磁闽 (7) 串联构成系列 A， 第三个常关电磁闽 (8) 与第四个常关电磁闽 (9) 串联构 成系列 B， 并联接入稳压器安全闽排放管线进入卸压箱 （5) 。
PCT/CN2013/089027 2012-12-13 2013-12-11 一种压水堆核电厂一回路事故排气系统 WO2014090142A1 (zh)

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CN112908500B (zh) * 2021-01-14 2024-05-10 中广核研究院有限公司 一种压力容器顶部不可凝结气体的体积控制方法
CN114999693B (zh) * 2022-06-01 2024-05-28 中国核动力研究设计院 压缩气体稳压反应堆防不凝气体进入堆芯的卸压保护系统

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ZA201504983B (en) 2016-10-26

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