Acknowledgement
This research work was funded by Harbin Engineering University. We also acknowledge the technical support project for Suzhou Nuclear Power Research Institute (SNPI) (NO.029-GN-B2018-C45-P.0.99-00003), the Foundation of Science and Technology on Reactor System Design Technology Laboratory (HT-KFKT-14-2017003) and the project of Research Institute of Nuclear Power Operation (No.RIN180149-SCCG).
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