SHEN Tong, XU Haixiang, YANG Xinguang, SONG Zhengfeng, LIU Kai, ZHAO He, ZHANG Haiming. DISPLACEMENT ANALYSIS FOR STRUCTURAL INTEGRITY TEST OF CONTAINMENT OF HPR1000 NUCLEAR POWER PLANT[J]. INDUSTRIAL CONSTRUCTION, 2021, 51(12): 1-6. doi: 10.13204/j.gyjzG21120605
Citation:
SHEN Tong, XU Haixiang, YANG Xinguang, SONG Zhengfeng, LIU Kai, ZHAO He, ZHANG Haiming. DISPLACEMENT ANALYSIS FOR STRUCTURAL INTEGRITY TEST OF CONTAINMENT OF HPR1000 NUCLEAR POWER PLANT[J]. INDUSTRIAL CONSTRUCTION, 2021, 51(12): 1-6. doi: 10.13204/j.gyjzG21120605
SHEN Tong, XU Haixiang, YANG Xinguang, SONG Zhengfeng, LIU Kai, ZHAO He, ZHANG Haiming. DISPLACEMENT ANALYSIS FOR STRUCTURAL INTEGRITY TEST OF CONTAINMENT OF HPR1000 NUCLEAR POWER PLANT[J]. INDUSTRIAL CONSTRUCTION, 2021, 51(12): 1-6. doi: 10.13204/j.gyjzG21120605
Citation:
SHEN Tong, XU Haixiang, YANG Xinguang, SONG Zhengfeng, LIU Kai, ZHAO He, ZHANG Haiming. DISPLACEMENT ANALYSIS FOR STRUCTURAL INTEGRITY TEST OF CONTAINMENT OF HPR1000 NUCLEAR POWER PLANT[J]. INDUSTRIAL CONSTRUCTION, 2021, 51(12): 1-6. doi: 10.13204/j.gyjzG21120605
This paper took the world's first HPR1000 nuclear power plant(NPP) of Fuqing 5 unit and Pakistan K2 unit in Karachi as the research object. Firstly, based on the ABAQUS finite element model, the overall test and theoretical analysis of containment structure of the HPR1000 NPP were carried out, the damage process of the containment structure under the LOCA accident was studied, and the weak links of the containment were clarified. According to NB/T 20017-2010 "Structural Integrity Test of Containments of Pressurized Water Reactor Nuclear Power Plants", the displacement test data of SIT test was analyzed, and the rationalization suggestions for the above standards were proposed according to the test process and results. The results showed that the test parameters of Fuqing 5 unit and Karachi K2 unit of NPP had the same trend with the test pressure; the test results were consistent with the theoretical analysis, and the displacement test results of the two units both met the standard design requirements of NB/T 20017-2010. It was suggested to increase the number of measuring points at the expected maximum horizontal diameter deformation and vertical deformation of the cylinder in the supplementary radial deformation measurement in NB/T 20017-2010, and increase the frequency of measuring points and data collection near the gate of the equipment.
TA K, NAKATOGAVA T, HISADA T, et al.Analytical Study on Dynamic Buckling of Reactor Containment Vessel[J].Nuclear Engineering and Design, 1997, 176(3):215-223.
[5]
HARSTEAD G A, MORRIS N F, UNSAL A I.Containment Vessel Stability Analysis[J].Nuclear Engineering and Design, 1983, 75(2):303-318.
[6]
FRANCESCO D M, GIANCARLO N, ENRICO Z, et al.Ensemble-Based Sensitivity Analysis of a Best Estimate Thermal Hydraulics Model:Application to a Passive Containment Cooling System of an AP1000 Nuclear Power Plant[J].Annals of Nuclear Energy, 2014, 73(11):200-210.
[7]
CHEN W R, WANG D Y, ZHANG Y S.Seismic Fragility Analysis of Nuclear Power Plants Based on the Substructure Method[J].Nuclear Engineering and Design, 2021, 382.https://doi.org/10.1016/j.nucengdes.2021.111389.
[8]
BASAK S, PAUL D K.Damage Evaluation of a RCC Containment Structure Subjected to Internal Pressure[J].International Journal of Engineering Science and Technology, 2012, 4(6):2823-2829.
[9]
ZHANG X.900 MW PWR Containment Mechanical Behavior Characteristics During Containment Test[J].Nuclear Engineering and Design, 2009, 239(9):1647-1652.
[10]
PRINJA N K, SHEPHERD D, CURLEY J.Simulating Structural Collapse of a PWR Containment[J].Nuclear Engineering and Design, 2005, 235(17):2033-2043.