The French Nuclear Island Equipment Design and Construction Rules of Association, “PWR Nuclear Island Mechanical Equipment Design and Construction Rules (RCC-M)”, Paris, 2000.
 J. H. Yu, “Analysis and Evaluation for the Reactor Vessels of CEFR,” M.S. Thesis, China Institute of Atomic Energy, Beijing, 2004.
 Z. Qin, “Research and Design of China Integral Reactor Plant Innovative Containment,” Nuclear Power Engineering, Vol. 27, No. 6, 2006, pp. 91-93.
 J.W. Wang, Z.H. Zhang, G.F. Wu and L.M. Fan, “Reactor Vessel Stress Analysis for CPR1000 Nuclear Power Plant,” Atomic Energy Science and Technology, Vol. 42, No. Supp1, 2008, pp. 459-499.
 W. Yang, L.G. Zheng and Y. Yang, “Stress and Fatigue Analysis for Outlet Nozzle of Nuclear Reactor Pressure Vessel,” Atomic Energy Science and Technology, Vol. 42, No. Supp1, 2008, pp. 505-508.
 X.Y. Cheng, X.W. Feng, G.Z. Li, B.Q. Zhu and B. Zhang, “Stress Analysis of Pressure Vessel Nozzle Based on AN-SYS/WORKBENCH,” Petro & Chemical Equipment, Vol. 14, No. 2, 2011, pp. 5-8.