• NUCLEAR TECHNIQUES
  • Vol. 46, Issue 6, 060601 (2023)
Yusheng LIU1,2, Sichao TAN1,*, Jianping JING2, Shaoxin ZHUANG2..., Dongyang LI1 and Nan WANG3|Show fewer author(s)
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
  • show less
    DOI: 10.11889/j.0253-3219.2023.hjs.46.060601 Cite this Article
    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 Copy Citation Text show less
    Schematic of break location in ACME facility
    Fig. 1. Schematic of break location in ACME facility
    RCS depressurization curves of different LOCA test condition
    Fig. 2. RCS depressurization curves of different LOCA test condition
    Pressure of RCS and second side of SG
    Fig. 3. Pressure of RCS and second side of SG
    Flow rate of cold leg in PRHR (a) and CMT (b) side loop
    Fig. 4. Flow rate of cold leg in PRHR (a) and CMT (b) side loop
    Transient heat transfer power of SGs
    Fig. 5. 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)
    Fig. 6. 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
    Fig. 7. Water level within C shape tube
    Outlet flow rate of PRHR
    Fig. 8. Outlet flow rate of PRHR
    Water temperature near PRHR HX within the IRWST (a) Case LOCA-01, (b) Case LOCA-02
    Fig. 9. Water temperature near PRHR HX within the IRWST (a) Case LOCA-01, (b) Case LOCA-02
    Injection flow rate of CMTs
    Fig. 10. Injection flow rate of CMTs
    Liquid level within CMT
    Fig. 11. Liquid level within CMT
    Mixing liquid level within the core region
    Fig. 12. Mixing liquid level within the core region

    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 1. Initial and boundary condition for LOCA tests at 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 2. The abbreviations of systems and equipments in ACME facility
    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
    Table 3. Chronology of major events obtained in ACME LOCA test
    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
    Download Citation