[1] | Li Zheng, Chen Chuqi, Zeng Wenjie, Li Ruokun. Research on Multi-objective Optimization of Parameters of Small Pressurized Water Reactor Nuclear Steam Supply Control System[J]. Nuclear Power Engineering, 2024, 45(6): 185-191. doi: 10.13832/j.jnpe.2024.06.0185 |
[2] | Wang Linna, Chen Chuqi, Zeng Wenjie, Chen Lekang, Li Ruokun. Simulation Study on Steam Dump Control System of Small Pressurized Water Reactor Nuclear Power Plant[J]. Nuclear Power Engineering, 2024, 45(2): 178-182. doi: 10.13832/j.jnpe.2024.02.0178 |
[3] | Li Xiaoquan. Failure Analysis and Reliability Improvement of Control System of Main Steam Isolation Valve in Nuclear Power Plants[J]. Nuclear Power Engineering, 2021, 42(1): 138-142. doi: 10.13832/j.jnpe.2021.01.0138 |
[4] | Guan Zhonghua, Qiu Zhifang, Jiang Xiaowei, Duan Yongqiang, Shen Yunhai, Fang Haoyu. Effect of Main Feedwater Isolation Modes on Mass and Energy Release and Containment Response for MSLB[J]. Nuclear Power Engineering, 2020, 41(2): 193-197. |
[5] | Qing Xianguo, Xiao Kai, Huang Ke, Chen Guanyu, Li Yiliang, Chen Zhi. Simulated Analysis of Pressure Control and Overpressure Problem of Reactor Cold Start-up with Nuclear Heating[J]. Nuclear Power Engineering, 2020, 41(5): 84-88. |
[6] | Chen Fei, Chen Shiyi, Meng Duiqiang. Open Failure Analysis of Parallel Slide Gate Valves in Steam Entrance of Steam Pump for PWR Auxiliary Water Supply System[J]. Nuclear Power Engineering, 2020, 41(4): 161-165. |
[7] | Yu Gang, Zhou Lusheng, Tao Zeyong, Zhang Baojun. Development of Inspection System for Weld Joint between Steam Generator and Reactor Coolant Pump in Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(5): 150-155. |
[8] | Xu Ying, Xu Jinquan, Yang Zongwei, Yu Hang. Analysis and Optimization of Frequent Isolation of Steam Generator Blowdown System in CPR1000 Nuclear Power Plant[J]. Nuclear Power Engineering, 2019, 40(6): 163-167. doi: 10.13832/j.jnpe.2019.06.0163 |
[9] | Yi Quanwei, Li Guangjun. Fault Analysis and Treatment of EAS Sump Line Isolation Valve[J]. Nuclear Power Engineering, 2018, 39(4): 112-115. doi: 10.13832/j.jnpe.2018.04.0112 |
[10] | Xiong Dongqing, He Zhenyu, Li Shixin, Shi Hong. Analysis of Development Difficulty for Main Steam Isolation Valves of Nuclear Power Plants[J]. Nuclear Power Engineering, 2018, 39(3): 138-142. doi: 10.13832/j.jnpe.2018.03.0138 |
[11] | Zhang Donglin, Yuan Shengyi, Wang Yuxiang, Guo Song, Yang Yong, Luo Shihong. Effect of Back Pressure on Pressurizer Safety Valve[J]. Nuclear Power Engineering, 2017, 38(S2): 172-174. doi: 10.13832/j.jnpe.2017.S2.0172 |
[12] | Ni Peng, Hui Hu, Wang Xiaodong, Lin Shaoxuan, Zhang Liyan, Chen Qingqi. Numerical Simulation of Hydraulically Expanded Tube-to-Tube Sheet Joints in Steam Generator[J]. Nuclear Power Engineering, 2015, 36(5): 204-207. doi: 10.13832/j.jnpe.2015.05.0204 |
[13] | Wang Chuang, Xiong Dongqing, Xu Guangzhen, Zhu Jie, Li Juan. Fault Mechanism Analysis of Single Loop Flow Deviation in PWR Nuclear Power Plants[J]. Nuclear Power Engineering, 2014, 35(5): 117-119. doi: 10.13832/j.jnpe.2014.05.0117 |
[14] | Zeng Chang, Lai Jianyong, Duan Yongqiang. Analysis and Improvement of Auxiliary Feedwater System Excessive Flow Based on 1D-3D Models[J]. Nuclear Power Engineering, 2014, 35(S1): 93-96. |
[15] | OuYang Yong, Jiang Xiaohua, Lu Xianghui. Improvement of Overpressure Protection in Cold Solid Condition for 1000MWe PWR NPP[J]. Nuclear Power Engineering, 2014, 35(S1): 113-116. |
[16] | BAO Yongke, TIAN Kuo, WANG Langlang. Root Reason and Solution Research of ASG TDFP Steam Inlet Isolating Valve Failure to Open[J]. Nuclear Power Engineering, 2013, 34(S2): 73-76. |
[17] | QIAO Piye, LIU Xi. Research and Improvement of Deaerators in Turbine Bypass Condition[J]. Nuclear Power Engineering, 2013, 34(S2): 62-64,69. |
[18] | WANG Baosheng, WANG Dongqing, ZHANG Jianmin, QIU Jianwen, WANG Jian. Research on Real-Time Simulation of Steam Dump Control System in PWR Nuclear Power Plants[J]. Nuclear Power Engineering, 2011, 32(5): 38-44. |
[19] | LIN Jiming, CHEN Peng, ZHANG Shishun. Study of Containment Over-Pressure Fragility Curve and Analysis of Opening Pressure for Containment Filtration and Exhaust System[J]. Nuclear Power Engineering, 2011, 32(3): 10-14. |
[20] | WANG Hai-tao, WU Xin-xin. Research on Creep and Fatigue Characteristics of MSIV at Elevated Temperature in HTR[J]. Nuclear Power Engineering, 2011, 32(S1): 18-21. |