[1] | Cheng Baoliang, He Gaoqing, Chen Siyuan, Chen Junrong. Finite Element Analysis of a Special Multi-bar Detection Manipulator[J]. Nuclear Power Engineering, 2024, 45(3): 174-178. doi: 10.13832/j.jnpe.2024.03.0174 |
[2] | Luo Juan, Qi Min, Tang Peng, Tang Long, Yao Di. Experimental Investigation on Fatigue Crack Propagation Behavior of Nuclear Pipe at High Temperature[J]. Nuclear Power Engineering, 2022, 43(S1): 142-145. doi: 10.13832/j.jnpe.2022.S1.0142 |
[3] | Zhang Ruikai, Liu Pan, Tan Jianping, Li Yue, Wang Dasheng, Tu Shandong. Calculation of Stress Intensity Factor of External Surface Crack on the Nozzle of Steam Generator in Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(5): 138-146. doi: 10.13832/j.jnpe.2022.05.0138 |
[4] | Zhu Bida, Shi Kaikai, Zheng Bin. Calculation of Stress Intensity Factor for Surface Cracks in FeCrAl Cladding under Force-Irradiation Coupling[J]. Nuclear Power Engineering, 2022, 43(S2): 177-181. doi: 10.13832/j.jnpe.2022.S2.0177 |
[5] | Chen Liang, Song Xiaoming, Pang Hua, Wang Kecheng, Huo Meng, Zeng Xiangguo. Calculation of Stress Intensity Factor of Zr-4 Cladding Tube by Flexibility Method[J]. Nuclear Power Engineering, 2019, 40(5): 202-206. |
[6] | Bao Xin, Liu Jingbo. Dynamic Finite Element Analysis Methods for Liquid Container Considering Fluid-Structure Interaction[J]. Nuclear Power Engineering, 2017, 38(2): 111-114. doi: 10.13832/j.jnpe.2017.02.0111 |
[7] | Luo Jiacheng, Zhang Yong, Li Pengzhou, Luo Juan, Sun Lei. Crack Growth Analysis of Ω Seal Overlay Weld Repair for CRDM[J]. Nuclear Power Engineering, 2016, 37(S2): 11-13. doi: 10.13832/j.jnpe.2016.S2.0011 |
[8] | Du Kun, Chu Qibao, Liang Mingbang, Shi Zuowei. FEM Seismic Analysis Method of Large Storage Tank in Consideration of Liquid Sloshing[J]. Nuclear Power Engineering, 2016, 37(6): 58-61. doi: 10.13832/j.jnpe.2016.06.0058 |
[9] | Liu Guixiang, Zhang Kun, Lin Song. Study on Flow-Induced Vibration for Pipe Conveying Fluid Based on Two Way Coupling Method with CFD and FEM[J]. Nuclear Power Engineering, 2016, 37(S2): 24-27. doi: 10.13832/j.jnpe.2016.S2.0024 |
[10] | Chen Xuede, Liu Zicai, Zhang Kun, Lin Song, Li Pengzhou, Li Xihua. Research on Shock Stress Reduction Factor in Shock Stress Evaluation of Stainless Steel Piping[J]. Nuclear Power Engineering, 2016, 37(S2): 96-98. doi: 10.13832/j.jnpe.2016.S2.0096 |
[11] | Li Nan, Han Zhi, Wang Jun, Wang Kunpeng, Zhang Chunming, Yi Dayong. FEM Analysis for Dropping Test of Fresh Fuel Cask[J]. Nuclear Power Engineering, 2015, 36(5): 18-21. doi: 10.13832/j.jnpe.2015.05.0018 |
[12] | Shao Xuejiao, ZHeng Liangang, Su Dongchuan, Fu Xiaolong, Kuang Linyuan. Study on Finite Simulation Technology for Seal Ring of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2015, 36(S2): 142-145. doi: 10.13832/j.jnpe.2015.S2.0142 |
[13] | Wang Dasheng, Liu Pan, Xiong Guangming. Fracture Mechanics Analysis for Inlet Nozzle of RPV with Pipe Load Considered[J]. Nuclear Power Engineering, 2015, 36(5): 120-123. doi: 10.13832/j.jnpe.2015.05.0120 |
[14] | NIE Jun-feng, ZHANG Hai-quan, LI Hong-ke, WANG Xin, ZHANG Zheng-ming. Dropping Accident Analysis of Liquid Storage Container using Finite Element Method[J]. Nuclear Power Engineering, 2013, 34(3): 144-147. |
[15] | HE Pan, LIU Caixue, WANG Yao, AI Qiong, SONG Jian. Study on Crack Leak Quantification of Pressure Pipeline[J]. Nuclear Power Engineering, 2012, 33(5): 32-35. |
[16] | ZHENG Bin, ZANG Fenggang, SUN Yingxue. Pressurized Thermal Shock Analysis for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2012, 33(1): 1-3,13. |
[17] | JIANG Xin, DING Shurong, HUO Yongzhong. Finite Element Simulation for Equivalent Elastic Properties of Dispersion Fuel Elements[J]. Nuclear Power Engineering, 2011, 32(3): 43-47. |
[18] | 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. |
[19] | LIU Li-ling, YI Li-qing, WEI Yong-tao. Equilibrium Iteration Algorithm for Analyzing Fluid-Structure Problems Using ALE Finite Element Method[J]. Nuclear Power Engineering, 2011, 32(S1): 137-140. |
[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. |