WO2014090144A1 - 一种压水堆核电厂反应堆冷却剂*** - Google Patents

一种压水堆核电厂反应堆冷却剂*** Download PDF

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Publication number
WO2014090144A1
WO2014090144A1 PCT/CN2013/089029 CN2013089029W WO2014090144A1 WO 2014090144 A1 WO2014090144 A1 WO 2014090144A1 CN 2013089029 W CN2013089029 W CN 2013089029W WO 2014090144 A1 WO2014090144 A1 WO 2014090144A1
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reactor
accident
water
power plant
nuclear power
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PCT/CN2013/089029
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English (en)
French (fr)
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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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Publication of WO2014090144A1 publication Critical patent/WO2014090144A1/zh
Priority to ZA2015/05016A priority Critical patent/ZA201505016B/en

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • 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

Definitions

  • the present invention relates to an accident response system for a reactor coolant system of a pressurized water reactor nuclear power plant, and specifically relates to a reactor coolant system for a pressurized water reactor nuclear power plant having severe accident response measures.
  • the reactor coolant system has complete and serious accident prevention and mitigation measures, including: high pressure exhaust of reactor pressure vessel, rapid pressure relief in primary circuit, steam The secondary side of the generator is discharged with passive residual heat.
  • the high pressure exhaust of the reactor pressure vessel 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 that only the only one in the reactor coolant system is The soda interface, to alleviate the consequences of the accident.
  • the rapid relief of the primary circuit performs the rapid pressure relief function under severe accidents, reduces the risk of high pressure melting piles under severe accidents, and avoids the phenomenon of high pressure melt injection that threatens the integrity of the containment.
  • the secondary side passive residual heat removal system of the steam generator operates to derive the residual heat of the core for a long time and maintain the reactor in a safe state.
  • the object of the present invention is to provide a pressurized water reactor nuclear power plant reactor coolant system with severe accident response measures suitable for the most widely used pressurized water reactor nuclear power plant (station) reactor coolant system, which can prevent and mitigate serious accidents. s consequence.
  • the invention is realized by the invention, a reactor coolant system of a pressurized water reactor nuclear power plant, which comprises an accident cooling water tank, and an emergency waste heat discharge cooler is arranged in the accident cooling water tank, and the emergency waste heat is discharged and cooled.
  • One end of the device is connected to the condensate line, and the condensate line is separated from the hydration line.
  • the condensate line is connected between the condensate line and the hydration line.
  • the emergency heat is discharged from the cooler.
  • One end is connected to the steam pipeline, and the two ends of the emergency waste heat discharge cooler are also respectively connected with the parallel emergency water supply tank.
  • the above-mentioned pressurized water reactor nuclear power plant reactor coolant system further includes a reactor pressure vessel, a normal exhaust gas enthalpy, a pressure relief tank interface, and an accidental exhaust gas enthalpy disposed at the top of the reactor pressure vessel, wherein the reactor pressure vessel and the normal exhaust gas ⁇ connected, the accident exhaust ⁇ is connected between the normal exhaust ⁇ and the reactor pressure vessel, and the accident venting ⁇ is also connected to the pressure relief tank interface.
  • the door of the accident exhaust valve is closed.
  • open the accident exhaust door to discharge the non-condensable gas at the top of the reactor pressure vessel.
  • the above-mentioned pressurized water reactor nuclear power plant reactor coolant system further includes a voltage regulator, a surge tube, a main pipe cold section connected to the reactor pressure vessel, and a main pipeline hot section, and one end of the surge tube is connected to the main pipeline hot section.
  • One end is connected to the regulator, and the top of the regulator is also equipped with a quick relief.
  • the top of the voltage regulator is equipped with a quick pressure relief ⁇ . Under severe accident conditions, the quick pressure relief ⁇ performs the discharge pressure relief function to prevent the high pressure fuse.
  • the invention has the advantages that a reactor coolant system for a pressurized water reactor nuclear power plant with severe accident response measures will be theoretically analyzed and experimentally verified, and will be applied to the design of three generations of domestic nuclear power plants.
  • the analysis shows that in the event of a serious accident, the accidental exhaust enthalpy at the top of the reactor pressure vessel can discharge half of the total volume of the reactor coolant system; the capacity of each series of rapid depressurization enthalpy is the sum of the three sets of safe enthalpy capacity. It can prevent the occurrence of high-pressure fusible accidents.
  • the residual heat of the core is extended by the secondary side passive residual heat removal system of the steam generator.
  • the reactor is in a safe state.
  • FIG. 1 is a schematic diagram of a reactor coolant system of a pressurized water reactor nuclear power plant provided by the present invention.
  • a reactor coolant system of a pressurized water reactor nuclear power plant is exhausted through a reactor pressure vessel, and the non-condensable gas at the top of the reactor is discharged to prevent the heat transfer from being affected by the core; Perform fast pressure relief to prevent high pressure melting; Provide a means to derive primary heat in severe accident conditions through the secondary side passive system of the steam generator.
  • a pressurized water reactor nuclear power plant reactor coolant system is provided with a high pressure exhaust gas enthalpy of the reactor pressure vessel at the top of the reactor pressure vessel, and a quick pressure relief ⁇ at the top of the pressure regulator, on the secondary side of the steam generator of each loop There is a secondary side passive residual heat removal system for the steam generator.
  • Each series includes one (or more) water supply tanks, one cooler, and the cooler is arranged at the bottom of the accident cooling water tank.
  • a reactor coolant system for a pressurized water reactor nuclear power plant comprising a reactor pressure vessel 1, the reactor pressure vessel 1 being respectively connected with a main pipeline cold section 7, a main pipeline hot section 5 and a normal exhaust enthalpy 11; a normal exhaust enthalpy 11 and The accident exhaust ⁇ 10 is connected, and the accident exhaust ⁇ 10 is connected to the pressure relief tank interface 19; one end of the undulating tube 8 is connected to the main pipe hot section 5, and the other end is connected to the regulator 2, the regulator 2 and the rapid pressure relief ⁇ 9 is connected, the main pipe hot section 5 is connected to the steam generator 3, the steam generator 3 is connected to the main pipe transition section 6, the main pipe transition section 6 is connected to the main pump 4, and the main pump 4 is connected to the main pipe cold section 7
  • the upper portion of the steam generator 3 is also connected to a steam line port 17 and a condensate line port 18, respectively, and both the steam line port 17 and the condensate line port 18 pass through the containment 20.
  • the accident cooling water tank 12 includes an emergency waste heat discharge cooler 13 and an emergency waste heat discharge cooler 13 One end is connected to the condensate line isolation ⁇ 15, the condensate line isolation ⁇ 15 is connected to the hydration line isolation ⁇ 16, and the condensate line interface 18 is connected between the condensate line isolation ⁇ 15 and the hydration line isolation ⁇ 16, emergency waste heat
  • the other end of the discharge cooler 13 is connected to the steam line port 17, and the two ends of the emergency waste heat discharge cooler 13 are also connected to the parallel emergency water supply tank 14, respectively.
  • the key equipment for the reactor coolant system to implement serious accident prevention and mitigation measures are:
  • the accident cooling water tank provides a heat sink for the discharge of the secondary side of the steam generator.
  • Accident cooling The water tank has an annular structure and is arranged on the outer side of the containment close to the top of the containment cylinder.
  • the civil structure is designed in unison with the containment. It is also designed with a water supply interface and a drain connection for water filling and draining during maintenance before starting.
  • the emergency waste heat discharge cooler consists of upper and lower tube sheets which pass through and are fixed to the tank wall of the accident cooling water tank.
  • the upper and lower tube sheets are respectively connected to the upper and lower heads.
  • the upper head is connected to the main steam line through a line
  • the lower head is connected to the condensate line through a line.
  • the emergency fill tank is a cylindrical container with an oval head.
  • the quick decompression ⁇ is in the closed state, and the overpressure protection of the reactor coolant system is realized by the safety of the regulator.
  • the pressure relief function is performed to prevent high pressure melting.
  • the door When the reactor is in normal operation, the door is closed and is the isolation barrier at the boundary of the circuit. In the event of an accident, the door is opened and the non-condensable gas at the top of the reactor pressure vessel is discharged.
  • the quick pressure relief ⁇ performs the discharge pressure relief function, and the operator manually opens the door according to the relevant serious accident handling procedures in the main control room or the remote shutdown station to complete the rapid pressure relief of the reactor coolant system.
  • the operator manually opens the door according to the relevant serious accident handling procedures in the main control room or the remote shutdown station to complete the rapid pressure relief of the reactor coolant system.
  • the isolation ⁇ of the condensate pipe is opened to connect the secondary side passive residual heat removal system of the steam generator.
  • the water condensed on the side of the cooler tube is injected into the secondary side of the steam generator, heated by the primary side reactor coolant to become steam, and enters the tube side of the cooler through the system steam line to transfer heat to the accident cooling water tank.
  • the water is condensed again into water, it returns to the secondary side of the steam generator to form a natural circulation.
  • the system transfers the heat from the reactor coolant to the cooler through the steam generator and then to the water in the cooling water tank, which in turn passes the heat out of the water in the cooling water tank to maintain the safety of the reactor.
  • the isolation ⁇ of the emergency water supply line, the water in the water supply tank is injected into the secondary side of the steam generator, and the secondary side water level of the steam generator during the operation of the compensation system The reduction.
  • the operator should manually close the isolation raft of the makeup line.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

一种压水堆核电厂反应堆冷却剂***，包括事故冷却水箱（12），事故冷却水箱（12）内设有应急余热排出冷却器（13），应急余热排出冷却器（13）的一端与冷凝水管线隔离阀（15）连接，冷凝水管线隔离阀（15）与补水管线隔离阀（16）连接，在冷凝水管线隔离阀（15）与补水管线隔离阀（16）之间连接有冷凝水管线接口（18），应急余热排出冷却器（13）的另一端与蒸汽管线接口（17）连接，应急余热排出冷却器（13）的两端还分别与并联的应急补水箱（14）连接。该***能够预防与缓解核电厂发生的严重事故的后果。

Description

说 明 书
一种压水堆核电厂反应堆冷却剂***
技术领域 本发明属于一种压水堆核电厂反应堆冷却剂***的事故应对***， 具体 涉及一种具备严重事故应对措施的压水堆核电厂反应堆冷却剂***。 背景技术
以往核电站在严重事故工况下， 缺少严重事故的预防与缓解措施， 该反 应堆冷却剂***具备完善的严重事故预防与缓解措施， 具体包括： 反应堆压 力容器高位排气、 一回路快速卸压、 蒸汽发生器二次侧非能动余热排出。 在事故工况下， 反应堆压力容器高位排气投入运行， 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***中只有唯一的汽水界面， 缓解事故后果。 一回路快速卸压在严重事故下执行快速卸压功能， 降低严重事故下高压 熔堆带来的风险， 避免出现威胁安全壳完整性的高压熔融物喷射现象。 在发生全厂断电， 同时电厂丧失能动堆芯余热排出能力的事故工况下， 蒸汽发生器二次侧非能动余热排除***运行， 能够长期导出堆芯余热， 维持 反应堆在安全状态。 发明内容
本发明的目的是提供一种具备严重事故应对措施的压水堆核电厂反应堆 冷却剂***适用于国内应用最为广泛的的压水堆核电厂 （站） 反应堆冷却剂 ***， 能够预防与缓解严重事故的后果。
本发明是这样实现的， 一种压水堆核电厂反应堆冷却剂***， 它包括事 故冷却水箱， 事故冷却水箱内设有应急余热排出冷却器， 应急余热排出冷却 器的一端与冷凝水管线隔离闽连接， 冷凝水管线隔离闽与补水管线隔离闽连 接， 在冷凝水管线隔离闽与补水管线隔离闽之间连接有冷凝水管线接口， 应 急余热排出冷却器的另一端与蒸汽管线接口连接， 应急余热排出冷却器的两 端还分别与并联的应急补水箱连接。
进一歩， 上述压水堆核电厂反应堆冷却剂***， 还包括反应堆压力容器、 正常排气闽、 卸压箱接口和设置在反应堆压力容器顶部的事故排气闽， 其中 反应堆压力容器与正常排气闽相连， 事故排气闽连接在正常排气闽与反应堆 压力容器之间， 事故排气闽还与卸压箱接口相连。 反应堆正常运行时， 事故 排气闽的闽门关闭； 事故发生时， 打开事故排气闽闽门即可排出反应堆压力 容器顶部的不可凝气体。
进一歩， 上述压水堆核电厂反应堆冷却剂***， 还包括稳压器、 波动管、 连接在反应堆压力容器上的主管道冷段和主管道热段， 波动管一端与主管道 热段相连， 一端连接稳压器， 稳压器顶部还设置有快速卸压闽。 本方案中再 稳压器顶部设置快速卸压闽， 在严重事故工况下， 快速卸压闽执行排放卸压 功能， 防止高压熔堆。
本发明的优点是， 一种具备严重事故应对措施的压水堆核电厂反应堆冷 却剂***将通过理论分析及实验验证， 并将应用于国内三代核电站的设计。 分析表明， 在发生严重事故时， 通过反应堆压力容器顶部的事故排气闽， 可 排出反应堆冷却剂***总容积一半的氢气； 每一系列快速卸压闽的容量是三 组安全闽容量的总和， 可防止发生高压熔堆事故； 在发生全厂断电， 同时电 厂丧失能动堆芯余热排出能力的事故工况下， 通过蒸汽发生器二次侧非能动 余热排出***， 长期导出堆芯余热， 维持反应堆在安全状态。
附图说明
图 1本发明所提供的一种压水堆核电厂反应堆冷却剂***示意图。
图中， 1反应堆压力容器； 2稳压器； 3蒸汽发生器； 4主泵； 5主管道 热段； 6主管道过渡段； 7主管道冷段； 8波动管； 9快速卸压闽； 10事故排 气闽； 11正常排气闽； 12事故冷却水箱； 13应急余热排出冷却器； 14应急 补水箱； 15冷凝水管线隔离闽； 16补水管线隔离闽； 17蒸汽管线接口； 18 冷凝水管线接口； 19卸压箱接口； 20安全壳。
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：
一种压水堆核电厂反应堆冷却剂***在严重事故工况下， 通过反应堆压 力容器事故排气闽，排出反应堆顶部的不可凝气体， 防止其影响堆芯的传热； 通过快速卸压闽， 执行快速卸压功能， 防止高压熔堆； 通过蒸汽发生器二次 侧非能动***， 为在严重事故工况下导出一回路热量提供手段。
一种压水堆核电厂反应堆冷却剂***在反应堆压力容器顶部设有反应堆 压力容器高位排气闽， 在稳压器顶部设有快速卸压闽， 在每个环路的蒸汽发 生器二次侧， 设有蒸汽发生器二次侧非能动余热排出***， 每个系列包括一 台 （或多台） 补水箱， 一台冷却器， 冷却器布置在事故冷却水箱的底部。
一种压水堆核电厂反应堆冷却剂***， 它包括反应堆压力容器 1， 反应 堆压力容器 1分别与主管道冷段 7、 主管道热段 5和正常排气闽 11连接； 正 常排气闽 11与事故排气闽 10连接， 事故排气闽 10与卸压箱接口 19连接； 波动管 8的一端与主管道热段 5连接， 另一端与稳压器 2连接， 稳压器 2与 快速卸压闽 9连接， 主管道热段 5与蒸汽发生器 3连接， 蒸汽发生器 3与主 管道过渡段 6连接， 主管道过渡段 6与主泵 4连接， 主泵 4与主管道冷段 7 连接， 蒸汽发生器 3的上部还分别与蒸汽管线接口 17和冷凝水管线接口 18 连接， 蒸汽管线接口 17和冷凝水管线接口 18均穿过安全壳 20。
事故冷却水箱 12包括应急余热排出冷却器 13， 应急余热排出冷却器 13 的一端与冷凝水管线隔离闽 15连接， 冷凝水管线隔离闽 15与补水管线隔离 闽 16 连接， 在冷凝水管线隔离闽 15与补水管线隔离闽 16 之间连接有冷凝 水管线接口 18， 应急余热排出冷却器 13的另一端与蒸汽管线接口 17连接， 应急余热排出冷却器 13的的两端还分别与并联的应急补水箱 14连接。
反应堆冷却剂***执行严重事故预防与缓解措施的关键设备有：
1 ) 事故冷却水箱
事故冷却水箱为蒸汽发生器二次侧非能动余热排出提供热阱。 事故冷却 水箱呈环状结构， 布置在安全壳外侧接近安全壳筒体顶部的位置， 其土建结 构与安全壳统一设计。 并设计有补水接口和排水接口， 以便启动前为水箱充 水和检修期间排水。
2) 应急余热排出冷却器
应急余热排出冷却器包含了上、 下两块管板， 管板穿过并固定在事故冷 却水箱的箱壁上。 上、 下管板分别与上、 下封头相连。 上封头通过管线与主 蒸汽管道相连， 下封头通过管线与凝水管道相连。
3 ) 应急补水箱
应急补水箱是一个带椭圆封头的圆柱形容器。 在***运行期间， 当蒸汽 发生器二次侧水位降低达到一定水位时， 注入管线上的隔离闽开启， 应急补 水箱中的水注入蒸汽发生器二次侧， 补偿***运行期间蒸汽发生器二次侧水 位的降低。
4) 快速卸压闽
在机组正常运行及设计基准事故期间， 快速卸压闽处于关闭状态， 由稳 压器安全闽实现反应堆冷却剂***的超压保护。 在严重事故工况下， 快速卸 压闽执行排放卸压功能， 防止高压熔堆。
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。
本发明的具体工作流程如下：
当发出事故排气信号时， 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。
在严重事故工况下， 快速卸压闽执行排放卸压功能， 在主控室或远程停 堆站由操作员根据有关的严重事故处理规程手动开启闽门， 完成反应堆冷却 剂***的快速卸压， 从而避免高压熔堆的发生以及安全壳的直接加热。
当发出蒸汽发生器二次侧非能动***启动信号时， 打开凝水管道的隔离 闽， 使蒸汽发生器二次侧非能动余热排出***连通。 ***投入后， 冷却器管 侧冷凝后的水注入蒸汽发生器二次侧， 被一次侧反应堆冷却剂加热后变成蒸 汽， 经***蒸汽管道进入冷却器的管侧， 将热量传递给事故冷却水箱的水后 再次冷凝为水， 再返回蒸汽发生器二次侧， 形成自然循环。 ***通过蒸汽发 生器将反应堆冷却剂中的热量传递到冷却器， 然后传递给冷却水箱中的水， 进而通过冷却水箱中水的蒸发将热量最终带出， 维持反应堆的安全。
在***投入运行后， 如果蒸汽发生器二次侧水位降低达到一定高度， 应 急补水管线的隔离闽， 补水箱中的水注入蒸汽发生器二次侧， 补偿***运行 期间蒸汽发生器二次侧水位的降低。 在注水结束后， 操作员应手动操作关闭 补水管线的隔离闽。

Claims

权 利 要 求
1、一种压水堆核电厂反应堆冷却剂***， 其特征在于： 它包括事故冷却 水箱 （12) ， 事故冷却水箱 （12) 内设有应急余热排出冷却器 （13) ， 应急 余热排出冷却器 （13) 的一端与冷凝水管线隔离闽 (15) 连接， 冷凝水管线 隔离闽 (15)与补水管线隔离闽 (16) 连接， 在冷凝水管线隔离闽 (15) 与 补水管线隔离闽 (16) 之间连接有冷凝水管线接口 （18) ， 应急余热排出冷 却器（13) 的另一端与蒸汽管线接口 （17)连接， 应急余热排出冷却器（13) 的两端还分别与并联的应急补水箱 （14) 连接。
2、根据权利要求 1所述的一种压水堆核电厂反应堆冷却剂***，其特征 在于： 还包括反应堆压力容器 （1) 、 正常排气闽 （11) 、 卸压箱接口 （19) 和设置在反应堆压力容器（1)顶部的事故排气闽 (10) ， 其中反应堆压力容 器（1)与正常排气闽 (11)相连， 事故排气闽 (10)连接在正常排气闽 (11) 与反应堆压力容器（1)之间， 事故排气闽 (10)还与卸压箱接口 （19)相连。
3、根据权利要求 2所述的一种压水堆核电厂反应堆冷却剂***，其特征 在于： 还包括稳压器 （2) 、 波动管 （8) 、 连接在反应堆压力容器 （1)上的 主管道冷段（7)和主管道热段（5)，所述波动管（8)—端与主管道热段（5) 相连，一端连接稳压器（2)，所述稳压器（2)顶部还设置有快速卸压闽（9)。
PCT/CN2013/089029 2012-12-14 2013-12-11 一种压水堆核电厂反应堆冷却剂*** WO2014090144A1 (zh)

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