NUCLEAR TECHNIQUES, Volume. 46, Issue 6, 060601(2023)

Investigation on natural circulation phenomena of LOCA with PRHR pipeline break in ACME facility

Yusheng LIU1,2, Sichao TAN1、*, Jianping JING2, Shaoxin ZHUANG2, Dongyang LI1, and Nan WANG3
Author Affiliations
  • 1Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, Harbin Engineering University, Harbin 150001, China
  • 2Nuclear and Radiation Safety Center, Beijing 100086, China
  • 3State Nuclear Power Technology R&D Center Co., Ltd., Beijing 102209, China
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    Figures & Tables(15)
    Schematic of break location in ACME facility
    RCS depressurization curves of different LOCA test condition
    Pressure of RCS and second side of SG
    Flow rate of cold leg in PRHR (a) and CMT (b) side loop
    Transient heat transfer power of SGs
    Inlet and outlet temperature of SG1 in LOCA-01 (a), SG1 in LOCA-02 (b), SG2 in LOCA-01 (c) and SG2 in LOCA-02 (d)
    Water level within C shape tube
    Outlet flow rate of PRHR
    Water temperature near PRHR HX within the IRWST (a) Case LOCA-01, (b) Case LOCA-02
    Injection flow rate of CMTs
    Liquid level within CMT
    Mixing liquid level within the core region
    • Table 1. Initial and boundary condition for LOCA tests at ACME facility

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      Table 1. Initial and boundary condition for LOCA tests at ACME facility

      参数

      Parameter

      数值 Value

      冷管段破口

      Break in CL (LOCA-01)

      PRHR管线破口

      Break in PRHR pipeline (LOCA-02)

      衰变功率Decay heat power / MW3.343.12
      稳压器压力Pressurizer pressure / MPa9.089.07
      RCS环路平均温度RCS average temperature / ℃291.5291.2

      蒸汽发生器二次侧出口压力

      Pressure of the secondary side of steam generator (SG) / MPa

      6.996.98
      SG二次侧液位Feed water level of SG / m3.623.64
      安注箱液位Level of Accumulator (ACC) / m1 3581 382
      堆芯补水箱水温Temperature of core makeup tank (CMT) / ℃30.033.7
      安全壳内置换料水箱水温Temperature of IRWST / ℃56.454.2
      IRWST液位Level of IRWST / m3.553.55
      等效破口直径Equivalent break diameter / cm55
    • Table 2. The abbreviations of systems and equipments in ACME facility

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      Table 2. The abbreviations of systems and equipments in ACME facility

      缩写

      Abbreviation

      中文全称

      Full Chinese name

      缩写

      Abbreviation

      中文全称

      Full Chinese name

      RX

      反应堆压力容器

      Reactor pressure vessel

      PRHR HX

      非能动余热排出热交换器

      Passive residual heat removal heat exchanger

      CL冷管段 Cold legPRHR非能动余热排出 Passive residual heat removal
      HL热管段 Hot legLOCA失水事故 Loss of coolant accident
      SG蒸汽发生器 Steam generatorSBLOCA小破口失水事故 Small break loss of coolant accident
      CMT堆芯补水箱 Core makeup tankSBO全厂断电事故 Station blackout accident
      ACC安注箱 AccumulatorPZR稳压器 Pressurizer
      PBL压力平衡管线 Pressure balance linePXS非能动堆芯冷却系统 Passive core cooling system
      DVI直接安注管线 Direct Vessel InjectionRCS反应堆冷却剂系统 Reactor coolant system
      ADS

      自动降压系统

      Automatic depressurization system

      IRWST

      安全壳内置换料水箱

      In containment refueling water storage tank

    • Table 3. Chronology of major events obtained in ACME LOCA test

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      Table 3. Chronology of major events obtained in ACME LOCA test

      台架设备动作 Action of facility equipment时间Time / s
      LOCA-01LOCA-02
      试验开始(S信号),主泵惰转 Test begins (S signal), Reactor pumps coastdown00
      破口阀打开 Break valve opens54
      SG1、SG2蒸汽关闭 Relief valves of SG1 & SG2 closed25
      CMT-1、CMT-2安注阀开启 Safety injection valves of CMT-1 & CMT-2 open15
      PRHR隔离阀开启 Isolation valve of PRHR pipeline opens310
      ADS1A、ADS1B开启 ADS1A and ADS1B open586624
      ADS2A、ADS2B开启 ADS2A and ADS2B open650686
      ACC1、ACC2安注阀开启 Safety injection valves of ACC-1 & ACC-2 open692750
      ADS3A、ADS3B开启 ADS3A and ADS3B open717/719755/755
      IRWST1、IRWST2安注阀开启 Safety injection valves of IRWST1 & IRWST2 open1 3751 399
      ADS4-1A失效,ADS4-2A开启 ADS4-1A starts failed while ADS4-2A opens1 3741 399
      ADS4-1B、ADS4-2B开启 ADS4-1B and ADS4-2B open1 4091 434
      IRWST安注开始 Safety injection of IRWST begins1 503/1 5061 531/1 543
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    Yusheng LIU, Sichao TAN, Jianping JING, Shaoxin ZHUANG, Dongyang LI, Nan WANG. Investigation on natural circulation phenomena of LOCA with PRHR pipeline break in ACME facility[J]. NUCLEAR TECHNIQUES, 2023, 46(6): 060601

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    Paper Information

    Category: Research Articles

    Received: Sep. 6, 2022

    Accepted: --

    Published Online: Jul. 5, 2023

    The Author Email:

    DOI:10.11889/j.0253-3219.2023.hjs.46.060601

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