AUTHOR=Zhu Dahuan , Sun Hongping , Zheng Bin , Huang Tao , Deng Jian , Xu Youyou , Luo Yuejian 

TITLE=Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR

JOURNAL=Frontiers in Energy Research

VOLUME=Volume 10 - 2022

YEAR=2022

URL=https://www.frontiersin.org/journals/energy-research/articles/10.3389/fenrg.2022.899405

DOI=10.3389/fenrg.2022.899405

ISSN=2296-598X

ABSTRACT=When the large pressurized water reactor in-vessel retention system (IVR) is put into operation, the outer wall of the reactor pressure vessel (RPV) will experience severe temperature fluctuations and be subjected to high internal pressure loads at the same time. In order to ensure the structural integrity of the RPV under such conditions, firstly, through the severe accident system program, the case that has the greatest impact on the pressure bearing thermal shock of the outer wall of the reactor pressure vessel was selected under the station black-out (SBO) accident. And then based on this case, the fracture mechanics finite element method was used to calculate and evaluate the pressure thermal shock (PTS) of the RPV, and the final crack size at the end of the life of the core barrel and the lower head was obtained by fatigue crack expansion calculation. The maximum ratio of stress intensity factor correction value and corresponding limit value under PTS transient load is about 0.874, which meets the requirements of RCC-M specification. The results of the study indicate that the RPV will not experience fracture failure when the IVR is put into service during the station black-out accident for HPR1000 nuclear power plant.