[1] | Xiong Jun, Lyu Weifeng, Guo Runchun, Gao Yaoyi, Jiang Zhenyu. Research on Evaluation Method of Actinide Nuclide Activities in Primary Coolant System of Pressurized Water Reactor Nuclear Power Plant[J]. Nuclear Power Engineering, 2024, 45(2): 47-52. doi: 10.13832/j.jnpe.2024.02.0047 |
[2] | Luan Xingjian, Wang Wen, Song Jiahao, Han Fei, Jiang Erhui, Cheng Kun, Yang Fan. Analysis on Flow Distribution Characteristics of Steam Generator under Natural Circulation Condition[J]. Nuclear Power Engineering, 2024, 45(4): 103-110. doi: 10.13832/j.jnpe.2024.04.0103 |
[3] | Xiong Furui, Zhang Wenzheng, Yuan Zhihao. Multi-fidelity Mechanical Model Matching and Updating of Primary Loop Supporting Structure[J]. Nuclear Power Engineering, 2023, 44(3): 243-248. doi: 10.13832/j.jnpe.2023.03.0243 |
[4] | Min Jidong, Li Jing, Hu Wensheng, Wu Xinzhuang. Research on Primary Vacuum System Based on Ejector[J]. Nuclear Power Engineering, 2023, 44(S2): 221-225. doi: 10.13832/j.jnpe.2023.S2.0221 |
[5] | Yan Xinlong, Li Yi, Luo Hanyu, Tian Ye. Transient Simulation Study of Primary Loop Nitrogen-typed Pressurization System[J]. Nuclear Power Engineering, 2022, 43(3): 33-37. doi: 10.13832/j.jnpe.2022.03.0033 |
[6] | Zhai Pengdi, Zhu Enping, Zhao Pengcheng, Wang Tianshi, Yu Tao. Research on the Key Influencing Factors of the Driving Force of the Primary Loop System of the Natural Circulation Lead-based Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(3): 66-73. doi: 10.13832/j.jnpe.2022.03.0066 |
[7] | Zhang Yan, Ma Lanqing, Jin Dongjie, Zhao Binbin. Optimization of Main Heat Exchanger Design for Primary Circuit of Low Temperature Nuclear Heating Reactor[J]. Nuclear Power Engineering, 2021, 42(1): 75-79. doi: 10.13832/j.jnpe.2021.01.0075 |
[8] | Ling Jun, Yang Yutao, Li Hongxia, Zang Yiming, Tan Ke, Yuan Jingqi, . Comprehensive Leakage Diagnosis Technology of Primary Loop Pressure Boundary of Nuclear Power Plants Based on Leakage Monitoring Data Synthesis[J]. Nuclear Power Engineering, 2021, 42(3): 188-193. doi: 10.13832/j.jnpe.2021.03.0188 |
[9] | Niu Yuhang, He Yanan, Wu Yingwei, Xiang Fengrui, Deng Chaoqun, Yu Yang, Su Guanghui, Qiu Suizheng, Tian Wenxi, Lu Tianyu. Analysis of Primary Loop System of High-Order Fully-Implicit Nuclear Reactor Based on MOOSE Platform[J]. Nuclear Power Engineering, 2021, 42(6): 50-57. doi: 10.13832/j.jnpe.2021.06.0050 |
[10] | Ma Jie, Zhang Longfei, Yu Ren, Peng Qiao, Hu Pengfei. Research on Accident Diagnosis Method for Reactor Primary Circuit System Based on SDG and PCA[J]. Nuclear Power Engineering, 2021, 42(3): 197-203. doi: 10.13832/j.jnpe.2021.03.0197 |
[11] | Xiong Furui, Ye Xianhui. Application of Modal Strain Energy in Dynamical Analysis of Reactor and Primary Loop System[J]. Nuclear Power Engineering, 2019, 40(3): 205-210. doi: 10.13832/j.jnpe.2019.03.0205 |
[12] | Zhang Zhao, Tang Qi, WEi Yanhui, SHen Rongfa, SHeng Guolong, Yan Junjie, Zhong Daotong. Research on Reactor Safety Analysis Method due to Thermal System Change of Secondary Circuit[J]. Nuclear Power Engineering, 2017, 38(1): 46-50. doi: 10.13832/j.jnpe.2017.01.0046 |
[13] | Lin Qinghu, Xu Tianfeng. IER-ICP-OES Measurement Study of Lithium in Primary Circuit Water Containing Boric Acid in Nuclear Power Plants[J]. Nuclear Power Engineering, 2017, 38(2): 118-121. doi: 10.13832/j.jnpe.2017.02.0118 |
[14] | Wang Hao, Yin Kaiju, Zhang Wei. Failure Analysis of Check Valve in Safety Injection System of a Nuclear Power Plant[J]. Nuclear Power Engineering, 2017, 38(3): 141-144. doi: 10.13832/j.jnpe.2017.03.0141 |
[15] | JIang Shenghan, Zhang Kun, Fan Kai, Li Zhibin, Li Pengzhou, Wang Yongchao. Research on Double Stage Vibration Isolation System of Vibratory Machine for Reactor Coolant System Based on Four-Pole Parameter Method[J]. Nuclear Power Engineering, 2017, 38(S2): 119-123. doi: 10.13832/j.jnpe.2017.S2.0119 |
[16] | Yao Yangui, Shi Yang, Zhang Kai, Lu Mingchao. Analysis of Relevant Problems of Shape Flow Resistance in Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(5): 83-86. doi: 10.13832/j.jnpe.2015.05.0083 |
[17] | Yu Huajin, Tang Long, Qi Min, Yu Danping. Measurement and Analysis of Thermal Strain in Emergency Decay Heat Removal System in CEFR[J]. Nuclear Power Engineering, 2015, 36(5): 156-160. doi: 10.13832/j.jnpe.2015.05.0156 |
[18] | CAI Qi, XIE Haiyan, ZHANG Yangwei. Study on Event Sequence of Loss-of-Coolant Accident of Primary Systems for MNPP Based on ESD[J]. Nuclear Power Engineering, 2012, 33(3): 83-88. |
[19] | ZUO Qiaolin, QIU Suizheng, LU Wei, SU Guanghui, TIAN Wenxi, WANG Sheng, XIAO Zejun. Numerical Simulation of Water Hammer Characteristics for Integral Reactor Primary Circuit[J]. Nuclear Power Engineering, 2012, 33(4): 85-90. |
[20] | QIN Huimin, YAN Changqi, WANG Jianjun. Optimal Design of Nuclear Reactor Primary Circuit Volume[J]. Nuclear Power Engineering, 2011, 32(4): 86-90. |