[1] | Chen Changyi, Xi Yanyan, Lu Yaheng, Wu Xuanlong, Wu Feng. Analysis of Influence of Expansion on Control Rod Drop in Nuclear Reactor at High Temperature[J]. Nuclear Power Engineering, 2024, 45(5): 108-114. doi: 10.13832/j.jnpe.2024.05.0108 |
[2] | Qi Yanqiang, Li Shunping, Peng Qian, Yan Meng, Chen Le, Dai Xun. Study on Low-cycle Fatigue Test Method for Zr-Sn-Nb Alloy Welded Sheets[J]. Nuclear Power Engineering, 2023, 44(S1): 188-193. doi: 10.13832/j.jnpe.2023.S1.0188 |
[3] | Tang Yuan, Wu Hao, Yan Dapeng, Huang Siyu, Li Qingzhao, Liu Yanting, Tang Jiankai, Fu Guozhong, Zhang Zhiqiang, Zhang Rui, Cui Zongze, Song Liwei. Research on Technology of Isolated Magnetoresistive Multipolar Resolver[J]. Nuclear Power Engineering, 2022, 43(S2): 189-195. doi: 10.13832/j.jnpe.2022.S2.0189 |
[4] | Du Kun, Zuo Yongde, Yuan Liang. Research of Ultimate Bearing Characteristics for Equipment Hatch of Nuclear Power Plant under External Pressure[J]. Nuclear Power Engineering, 2020, 41(6): 106-110. |
[5] | Jiang Xinyue, Wang Naxiu, Su Bo, Chen Yushuang, Kong Xiangbo, Lu Huiju, Fu Yuan. Structural Design and Finite Element Analysis of a Normally-Closed Finned Freeze Valve[J]. Nuclear Power Engineering, 2019, 40(6): 149-154. doi: 10.13832/j.jnpe.2019.06.0149 |
[6] | Liu Zhenhai, Chen Ping, Zhou Yi, Li Wenjie, Zhang Kun, Xing Shuo, Miao Yifei. 3D Simulation of Fuel Performance with Missing Pellet Surface Defect[J]. Nuclear Power Engineering, 2018, 39(2): 180-184. doi: 10.13832/j.jnpe.2018.0180 |
[7] | Tang Changbing, LI Wenjie, Chen Ping, LI Yuanming, ZhOu Yi, LI Wei. Numerical Research on Irradiation-Thermal-Mechanical Coupling Behavior of FCM Fuel[J]. Nuclear Power Engineering, 2017, 38(S2): 16-19. doi: 10.13832/j.jnpe.2017.S2.0016 |
[8] | Lu Xifeng, Wang Xinjun, Ai Honglei, Lyu Yongbo, HE Feng. Creep-Fatigue Analysis and Evaluation of Thorium-Based Molten Salt Reactor Loop Pipe[J]. Nuclear Power Engineering, 2017, 38(1): 56-59. doi: 10.13832/j.jnpe.2017.01.0056 |
[9] | Liu Zhenhai, Li Wenjie, Chen Ping, Li Yuanming, Zhou Yi, Zhang Kun, Xing Shuo. FCM Fuel Thermal Performance Analysis[J]. Nuclear Power Engineering, 2016, 37(6): 150-154. doi: 10.13832/j.jnpe.2016.06.0150 |
[10] | 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 |
[11] | Zhang Tianyi, Zhang Zhenxing, hu Lina, Xu Yu. Effect of Tube Structural Style on Thermal Stress in CEFR Intermediate Heat Exchanger[J]. Nuclear Power Engineering, 2015, 36(5): 148-151. doi: 10.13832/j.jnpe.2015.05.0148 |
[12] | XU Xiao, JIN Ting, YANG Jingchao. Theory Resolution of Extraction-Insertion Force for Irradiation Capsule[J]. Nuclear Power Engineering, 2014, 35(2): 146-149. |
[13] | Wang Xinjun, Lu Xifeng, ai Honglei, He Feng, Yuan Yanli, LÜ Yongbo. Optimization Analysis of High-Energy Piping System[J]. Nuclear Power Engineering, 2014, 35(4): 114-118. doi: 10.13832/j.jnpe.2014.04.0114 |
[14] | LU Xifeng, ZHANG Yixiong, AI Honglei, WANG Xinjun, HE Feng. Study on Mixed Analysis Method for Fatigue Analysis of Oblique Safety Injection Nozzle on Main Piping[J]. Nuclear Power Engineering, 2014, 35(2): 86-89. |
[15] | OU Ming-xiong, WANG Yan, YAN Jian-hua, SHENG Jiang. Effect of Dynamic Structure Stiffness on Rotor Characteristics of Vertical Pump[J]. Nuclear Power Engineering, 2013, 34(6): 36-39. |
[16] | LU Jianming, OUYANG Guangyao, ZHANG Ping, RONG Bojun. Identification of Complex Model Thermal Boundary Conditions Based on Exterior Temperature Measurement[J]. Nuclear Power Engineering, 2012, 33(5): 50-53,68. |
[17] | XIONG Guang-ming, DENG Xiao-yun, JIN Ting. Comparative Analysis of Two Different Finite Models for SG Steam Outlet Nozzle Assembly[J]. Nuclear Power Engineering, 2011, 32(S1): 44-47. |
[18] | HUI Hu, LI Zhi-qiang, ZHANG Li-yan, JIAO Ming, LI Pei-ning. Study on Numerical Simulation of Bursting Pressure of Steam Generator Tubes with Local Wall-Thinning[J]. Nuclear Power Engineering, 2011, 32(S1): 69-72. |
[19] | LIU Zhi-wei, WANG Guo-zhen, XUAN Fu-zhen, LIU Zhang-jun, TU Shan-dong. Study on Failure Assessment Curves for Safe End of Nuclear Pressure Vessels[J]. Nuclear Power Engineering, 2011, 32(S1): 169-172,178. |
[20] | JIANG Naibin, ZANG Fenggang, ZHANG Limin, ZHANG Chuanyong. Seismic Analysis on Integral Reactor System with Large-Scale Three-Dimensional Finite Element Method[J]. Nuclear Power Engineering, 2011, 32(2): 44-47,58. |