Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2017, Vol. 28 ›› Issue (6): 73 doi: 10.1007/s41365-017-0233-8


Thermal-hydraulic and stress analysis of AP1000 reactor containment during LOCA in dry cooling mode

Sh. Sheykhi1, S. Talebi1, M. Soroush2, E. Masoumi1   

  1. 1 Department of Energy Engineering and Physics, Amirkabir University of Technology (Tehran Polytechnic), 424 Hafez Avenue, P.O. Box 15875-4413, Tehran, Iran
    2 Young Researchers and Elite Club, Islamic Azad University, South Tehran Branch, Tehran, Iran
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Sh. Sheykhi, S. Talebi, M. Soroush, E. Masoumi. Thermal-hydraulic and stress analysis of AP1000 reactor containment during LOCA in dry cooling mode.Nuclear Science and Techniques, 2017, 28(6): 73     doi: 10.1007/s41365-017-0233-8


Some kinds of break in the reactor coolant system may cause the coolant to exit rapidly from the failure site, which leads to the loss of coolant accident (LOCA). In
this paper, a stress analysis of an AP1000 reactor containment is performed in an LOCA, with the passive containment cooling system (PCCS) being available and not available for cooling the wall’s containment. The variations in the mechanical properties of the wall’s containment, including elastic modulus, strength, and stress, are analyzed using the ABAQUS code. A general two-phase model is applied for modeling thermal-hydraulic behavior inside the containment. Obtained pressure and temperature from thermal-hydraulic models are considered as boundary conditions of the ABAQUS code to obtain distributions of temperature and stress across steel shell of the containment in the accident. The results indicate that if the PCCS fails, the peak pressure inside the containment exceeds the
design value. However, the stress would still be lower than the yield stress value, and no risk would threaten the integrity of the containment.

Key words: Two-phase flow, LOCA, Containment integrity, AP1000 reactor