• NUCLEAR TECHNIQUES
  • Vol. 46, Issue 12, 120603 (2023)
Xi BAI1, Peiwei SUN1、*, Gang LUO2, Huasong CAO3, and Xinyu WEI1
Author Affiliations
  • 1School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
  • 2Nuclear Power Institute of China, Chengdu 610012, China
  • 3Xi'an Thermal Power Research Institute Co. Ltd, Xi'an 710054, China
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    DOI: 10.11889/j.0253-3219.2023.hjs.46.120603 Cite this Article
    Xi BAI, Peiwei SUN, Gang LUO, Huasong CAO, Xinyu WEI. Sensitivity analysis of large leakage sodium-water reaction protection system critical parameters with paralleling steam generators in a sodium-cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(12): 120603 Copy Citation Text show less
    Structural diagram of the secondary loop in sodium-cooled fast reactor
    Fig. 1. Structural diagram of the secondary loop in sodium-cooled fast reactor
    Relationship diagram of large leakage SWR model
    Fig. 2. Relationship diagram of large leakage SWR model
    Diagram of hydrogen bubble transition from the spherical to columnar model
    Fig. 3. Diagram of hydrogen bubble transition from the spherical to columnar model
    Diagram of SWR experiment system
    Fig. 4. Diagram of SWR experiment system
    Fitting curve of pressure input in reaction zone
    Fig. 5. Fitting curve of pressure input in reaction zone
    Comparison of calculated and experimental pressure at secondary loop critical equipment
    Fig. 6. Comparison of calculated and experimental pressure at secondary loop critical equipment
    Pressure response of secondary loop critical equipment
    Fig. 7. Pressure response of secondary loop critical equipment
    Flow rate response of sodium in SGs
    Fig. 8. Flow rate response of sodium in SGs
    Pressure response of tank gas chamber
    Fig. 9. Pressure response of tank gas chamber
    Sodium flow rate of damaged SG rupture disk
    Fig. 10. Sodium flow rate of damaged SG rupture disk
    Sodium release flow rate of damaged SG module at different liquid rupture disk bursting pressures
    Fig. 11. Sodium release flow rate of damaged SG module at different liquid rupture disk bursting pressures
    Sodium release flow rate of damaged SG module at different rupture disk bursting delay times
    Fig. 12. Sodium release flow rate of damaged SG module at different rupture disk bursting delay times
    Sodium release flow rate of damaged SG module at different liquid rupture disk locations
    Fig. 13. Sodium release flow rate of damaged SG module at different liquid rupture disk locations
    Sodium release flow rate damaged SG module at different release pipe lengths
    Fig. 14. Sodium release flow rate damaged SG module at different release pipe lengths
    Sodium release flow rate of damaged SG module at different primary accident discharge tank volumes
    Fig. 15. Sodium release flow rate of damaged SG module at different primary accident discharge tank volumes
    设备Equipment参数Parameter
    蒸汽发生器爆破片位置Location of rupture disk at SG下腔室 Bottom chamber
    SG爆破片爆破压力Bursting pressure of rupture disks at SG / MPa1.0
    缓冲罐气腔爆破片爆破压力Bursting pressure of rupture disk at the surge tank gas chamber / MPa0.35

    二级事故排放罐气腔爆破片爆破压力

    Bursting pressure of rupture disk at secondary accident discharge tank gas chamber / MPa

    0.5
    爆破片爆破延迟时间Bursting delay time of rupture disks / s0.02
    Table 1. Critical parameters of protection system in secondary loop

    设备

    Equipment

    压力峰值

    Peak pressure / MPa

    压力峰值出现时间

    Time of the peak pressure / s

    泵Pump0.8940.139
    中间热交换器Intermediate heat exchanger1.3290.188
    钠流量分配器Sodium flow distributor1.0700.049
    事故SG模块Damaged SG module2.0030.052
    正常模块蒸汽发生器Normal SGs module0.6690.197
    缓冲罐Surge tank0.2412.500
    一级事故排放罐Primary accident discharge tank0.0522.500
    二级事故排放罐Secondary accident discharge tank0.0512.500
    Table 2. Critical parameters of protection system in secondary loop

    敏感性参数

    Sensitivity parameter

    模拟工况

    Simulation conditions

    SWR压力

    峰值

    SWR

    pressure

    spike

    / MPa

    IHX压力

    峰值

    IHX

    pressure

    spike

    / MPa

    PADT压力

    峰值

    PADT

    pressure

    spike

    / MPa

    SH爆破

    时间

    SH

    bursting

    time

    / s

    EV爆破

    时间

    EV

    bursting

    time

    / s

    出口报

    警时间

    Outlet

    alarming

    time

    / s

    入口报

    警时间

    Input

    alarming time

    / s

    液相爆破片爆破压力

    Bursting pressure of liquid

    rupture disks

    0.8 MPa1.9931.3270.0520.0270.0330.0240.04
    1.0 MPa2.0031.3290.0520.0280.0360.0240.04
    1.2 MPa2.0571.3420.0520.0370.0400.0240.042

    爆破片爆破延迟时间

    Bursting delay time of

    rupture disks

    0.02 s2.0031.3290.0520.0280.0360.0240.04
    0.07 s2.1471.4110.0520.0780.0860.0240.04
    0.12 s2.1471.4410.0520.1280.1360.0240.04

    液相爆破片位置

    Location of the liquid

    rupture disks

    上腔室

    Upper chamber

    1.9971.3390.0520.0330.0360.0240.04

    下腔室

    Bottom chamber

    2.0031.3290.0520.0280.0360.0240.04

    泄放管长度

    Length of release pipe

    减小到80%

    Decreased to

    80 percentage

    1.9831.3090.0520.0280.0360.0240.04
    不变Unchanged2.0031.3290.0520.0280.0360.0240.04

    增大到1.2

    Increased to

    120 percentage

    2.0201.3440.0520.0290.0360.0240.04

    一级事故排放罐体积

    Volume of PADT

    减小到50%

    Decreased to

    50 percentage

    2.0031.3290.0540.0280.0360.0240.040
    不变Unchanged2.0031.3290.0520.0280.0360.0240.04

    增大到1.5

    Increased to

    150 percentage

    2.0031.3290.0510.0280.0360.0240.04
    Table 3. Maximum pressure of the critical equipment in secondary loop
    Xi BAI, Peiwei SUN, Gang LUO, Huasong CAO, Xinyu WEI. Sensitivity analysis of large leakage sodium-water reaction protection system critical parameters with paralleling steam generators in a sodium-cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(12): 120603
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