[1] | Dong Yuanyuan, Luo Ying, Du Hua, Hu Tian, Wang Xiaotong. Study on Irradiation Temperature Impact on Irradiation Embrittlement Behavior of RPV Material[J]. Nuclear Power Engineering, 2024, 45(S2): 102-109. doi: 10.13832/j.jnpe.2024.S2.0102 |
[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] | Guo Yanhui, Sun Zaozhan, Sun Haitao, Xu Chaoliang, Liu Xiangbing, Tao Jun. Construction and Analysis of Irradiation Damage Prediction Model for Autonomous Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2022, 43(S1): 55-59. doi: 10.13832/j.jnpe.2022.S1.0055 |
[5] | Luan Xingfeng, Zhao Chuanli, Xu Feng, Tao Hongxin, Zhang Jiangtao, Gao Xuan, Tao Ge. Irradiation Embrittlement Time-limited Aging Analysis of Reactor Pressure Vessel for Qinshan Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(S1): 51-54. doi: 10.13832/j.jnpe.2022.S1.0051 |
[6] | 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 |
[7] | Shangguan Bin, Li Chengliang. Non-Destructive Evaluation Technology for Irradiation Surveillance of Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2019, 40(6): 59-63. doi: 10.13832/j.jnpe.2019.06.0059 |
[8] | 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 |
[9] | Zhang Meng, Peng Sitong, Wang Chen, Lei Chao. Evaluation of Reactor Pressure Vessel Irradiation Embrittlement of VVER-1000 Nuclear Power Unit[J]. Nuclear Power Engineering, 2018, 39(S2): 168-172. doi: 10.13832/j.jnpe.2018.S2.0168 |
[10] | 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 |
[11] | 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 |
[12] | Sun Kai, Feng Mingquan, Li Guoyun, Wu Yazhen, Li Furong. Assessment of Irradiation Embrittlement of Domestic RPV Material[J]. Nuclear Power Engineering, 2017, 38(S1): 125-128. doi: 10.13832/j.jnpe.2017.S1.0125 |
[13] | 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 |
[14] | 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 |
[15] | Jiang Guofu, Li Guoyun, Luan Xingfeng, Zhang Haisheng, Huang Juan, Yang Xu, Cao Jiebao, Sun Kai. Irradiation Surveillance of RPV for Unit 1&2 of QinshanⅡNPP[J]. Nuclear Power Engineering, 2015, 36(S1): 187-190. doi: 10.13832/j.jnpe.2015.S1.0187 |
[16] | 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. |
[17] | QIU Tian, LUO Ying, MA Shuli, ZHOU Gaobin, LI Zhangxiang. Research of 60-Year Design Life for Domestic PWR Reactor Pressure Vessel Based on Irradiation Embrittlement[J]. Nuclear Power Engineering, 2013, 34(S1): 103-108,115. |
[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] | ZHU Zheng-qing. Research and Development of Modern Large-Scale Reactor Pressure Vessel Materials[J]. Nuclear Power Engineering, 2011, 32(S2): 1-4,8. |