[1] | Dong Yuanyuan, Zhang Yabin, Du Hua, Wang Xuxin, Zhao Wei. Study on Cyclic Relaxation Characteristics of C-ring for Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2022, 43(4): 65-69. doi: 10.13832/j.jnpe.2022.04.0065 |
[2] | Yu Peng, Yang Xiaoming, Ma Rubing, Yuan Yidan. Study on Modified θ-projection Creep Model of Reactor Pressure Vessel Steel SA533B[J]. Nuclear Power Engineering, 2022, 43(4): 86-90. doi: 10.13832/j.jnpe.2022.04.0086 |
[3] | Fu Qiang, Min Yuansheng, Liu Chuan, Li Meifu, Li Yuguang. Study of Residual Stress Distribution of Large Ring-type Dissimilar Metal Weld in Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2022, 43(3): 123-128. doi: 10.13832/j.jnpe.2022.03.0123 |
[4] | Hu Chenxu, Sun Jiawei, Li Bingqian. Research on PA Ultrasonic Inspection Technology in RPV[J]. Nuclear Power Engineering, 2021, 42(2): 148-152. doi: 10.13832/j.jnpe.2021.02.0148 |
[5] | Jiang Xing, Weng Yu, Wang Haijun. Study on Heat Distribution Characteristics of Direct Safety Injection of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2021, 42(5): 119-122. doi: 10.13832/j.jnpe.2021.05.0119 |
[6] | Zhu Guangqiang, Wei Yanhui. Status Assessment of RPV Irradiation Embrittlement[J]. Nuclear Power Engineering, 2018, 39(4): 39-42. doi: 10.13832/j.jnpe.2018.04.0039 |
[7] | Wang Xiaobing, Long Tao, Fan Yijun, Wen Xiaojun. Optimization Analysis about Pre-Tightening Technology of Stud for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2018, 39(6): 64-68. doi: 10.13832/j.jnpe.2018.06.0064 |
[8] | Li Chengliang, Li Yuanfei, MO Huajun, Liu Feihua, Chen Jun, SHu Guogang. Irradiation Damage Effects on Microstructure of Reactor Pressure Vessel Steels[J]. Nuclear Power Engineering, 2017, 38(S1): 54-57. doi: 10.13832/j.jnpe.2017.S1.0054 |
[9] | CHEN Zhenwei, WU Chaorong, GUAN Jianwei, XING Rujun, YANG Chunle, GUAN Chunxiang. Technology Improvement for Reactor Pressure Vessel of Ling’ao Phase II Nuclear Power Station, Shenzhen, Guangdong, 518124, China[J]. Nuclear Power Engineering, 2015, 36(1): 68-71. doi: 10.13832/j.jnpe.2015.01.0068 |
[10] | Hong Maocheng, Yu Zhe, Lin Ge, Xiao Xuezhu, Ma Guanbing. Calculations and Simulation of Ultrasonic Inaccessible Zones for Outlet to Shell Weld in RPV[J]. Nuclear Power Engineering, 2015, 36(4): 118-121. doi: 10.13832/j.jnpe.2015.04.0118 |
[11] | Nie Zhiping, Wang Nianwei, Dong Wanfu. Analysis and Processing of Main Bolt Gluing in RPV[J]. Nuclear Power Engineering, 2015, 36(2): 109-112. doi: 10.13832/j.jnpe.2015.02.0109 |
[12] | ZHANG Lin, CHU Qibao, FANG Yonggang. Nuclear Safety Review on Exceeding Allowable Flaw Treatment of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2014, 35(2): 84-85,97. |
[13] | ZHANG Li-ping, ZHENG Lian-gang, LU Yue-chuan, LIU Wen-jin. Analysis of Fast Fracture of Core Region of RPV[J]. Nuclear Power Engineering, 2013, 34(5): 30-32. |
[14] | DANG Ying, WEN Yao-ceng, QIU Shao-yu, CHEN Yong, LUO Qiang, LI Chuan-qian. Study on Performance of Novel Overlaying Welding Materials on the Sealing Face of RPV[J]. Nuclear Power Engineering, 2013, 34(5): 84-88. |
[15] | LIU Jinhua, WEN Yan, ZHANG Xuemei, HUO Songmin, GONG Bin, HE Yanchun. Corrosion Properties of Sealing Surface Material for RPV under Abnormal Working Conditions[J]. Nuclear Power Engineering, 2012, 33(1): 83-87. |
[16] | XIONG Guangming, DUAN Yuangang, DENG Xiaoyun, TAN Yu, JIN Ting, YANG Nengren. Numerical Simulation Research on C-ring of CPR1000 Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2012, 33(6): 9-12. |
[17] | ZHU Zheng-qing. Research and Development of Modern Large-Scale Reactor Pressure Vessel Materials[J]. Nuclear Power Engineering, 2011, 32(S2): 1-4,8. |
[18] | WANG Yongjiao, YANG Zhipeng. Analysis and Treatment of Cladding Layer Defects on Outlet Nozzle of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2011, 32(4): 83-85. |
[19] | TAN Xiao-hui. Effect of Fabrication Error of Reactor Pressure Vessel on Its Load-Bearing Ability[J]. Nuclear Power Engineering, 2011, 32(S1): 201-204. |
[20] | ZHANG Tian-yi, WAN Li, SHI Li, ZHANG Chuan-yong. FE Simulation of Bolt-up Process for Press-Retraining Bolts of HTR-PM Pressure Vessel[J]. Nuclear Power Engineering, 2011, 32(S1): 54-56. |