[1] | Wang Ningyuan, Chen Deqi, Liu Hanzhou, Bu Shanshan. Experimental Study on Single-phase Flow-induced Vibration Mechanism in Helical Coiled Tubes[J]. Nuclear Power Engineering, 2024, 45(S2): 174-179. doi: 10.13832/j.jnpe.2024.S2.0174 |
[2] | Wang Shuaiquan, Zhang Kai, Xiong Zhenqin, Shi Linpeng. Effect of Baffle on Flow Induced Vibration of Heat Exchange Tubes[J]. Nuclear Power Engineering, 2024, 45(2): 123-129. doi: 10.13832/j.jnpe.2024.02.0123 |
[3] | Liu Shiwen, He Ronghui, Yang Zhao, Wang Jiarui, Chen Shuang, Lai Jianyong, Li Yi. Numerical Simulation Research on Flow-Induced Vibration Characteristics of Fluid-Conveying Pipe Network[J]. Nuclear Power Engineering, 2022, 43(1): 187-191. doi: 10.13832/j.jnpe.2022.01.0187 |
[4] | Zhang Yu, He Chao, Sun Lei. Numerical Investigation on Flow Induced Vibration of Distributed Circular Tube Bundle[J]. Nuclear Power Engineering, 2022, 43(S1): 111-115. doi: 10.13832/j.jnpe.2022.S1.0111 |
[5] | Ding Lin, He Haoyu, Yang Zuomei, Zhang Li, Yang Lin. Thermal-Fluid-Solid Coupling Characteristics of a Circular Tube in Two Degrees of Freedom Flow-Induced Vibration[J]. Nuclear Power Engineering, 2021, 42(2): 131-136. doi: 10.13832/j.jnpe.2021.02.0131 |
[6] | Feng Xiaodong, Su Wentao, Ma Yu, Wang Lei, Li Xiaobin. Analysis of Flow-Induced Vibration of HP-Cooler Coil on Reactor Coolant Pump[J]. Nuclear Power Engineering, 2020, 41(6): 101-105. |
[7] | Shen Pingchuan, Liu Qing, Qi Huanhuan, Huang Xuan, Liu Jian, Chen Guo. Study on Flow-Induced Vibration Damping Simulation of Heat Exchanger Tube in Non-Uniform Two-Phase Flow[J]. Nuclear Power Engineering, 2020, 41(6): 116-119. |
[8] | Zhang Botao, Zhu Yechen, Gong Shengjie, Gu Hanyang. Experimental Study on Flow Induced Vibration of Different Size Strips of Fuel Rod Bundles[J]. Nuclear Power Engineering, 2019, 40(5): 192-196. |
[9] | Zhu Yong, Han Tonghang, Ren Hongbing. Analysis of Effect of Steam Generator Anti-Vibration Bars Shift on Flow Induced Vibration and Wear of Tube Bundle[J]. Nuclear Power Engineering, 2016, 37(5): 29-32. doi: 10.13832/j.jnpe.2016.05.0029 |
[10] | Jiang Tianze, Li Pengzhou, Ma Jianzhong, Gao Lixia, Lai Jiang. Three Key Mechanical Problems of Flow Induced Vibration of Tube Bundles in Two-Phase Flow[J]. Nuclear Power Engineering, 2016, 37(S2): 14-19. doi: 10.13832/j.jnpe.2016.S2.0014 |
[11] | Yu DanPing, Ma Jianzhong, Xi Zhide, Yang Jie. Review of Experimental Research of Flow-Iinduced Vibration of Reactor Internals[J]. Nuclear Power Engineering, 2016, 37(S2): 47-51. doi: 10.13832/j.jnpe.2016.S2.0047 |
[12] | Lai Jiang, Yang Jie, Xi Zhide, Sun Lei, Li Pengzhou. Analysis of Flow-Induced Vibration of Nuclear Reactor Internals[J]. Nuclear Power Engineering, 2016, 37(S2): 28-31. doi: 10.13832/j.jnpe.2016.S2.0028 |
[13] | Zhang Xiaoling, Li Tianyong, Ma Jianzhong, Liu Litao, Li Pengzhou. Test Studies of Flow Induced Vibration for Fuel Assembly[J]. Nuclear Power Engineering, 2016, 37(S2): 44-46. doi: 10.13832/j.jnpe.2016.S2.0044 |
[14] | Wu Licun, Lu Daogang, Liu Yu, ZHong Haoliang, Liu Guangyao. Investigation on Flow-Induced Vibration Mechanism of Fuel Rods Fixed by Wrapped Wire[J]. Nuclear Power Engineering, 2015, 36(2): 147-150. doi: 10.13832/j.jnpe.2015.02.0147 |
[15] | Xu Xiao, Ma Ruoqun, Zhang Guihe, Wang Dasheng. Flow Induced Vibration of RPV Upper Internals Support Columns[J]. Nuclear Power Engineering, 2014, 35(6): 61-65. doi: 10.13832/j.jnpe.2014.06.0061 |
[16] | Feng Zhipeng, Zhang Yixiong, Zang Fenggang. Study on Flow Induced Vibration Characteristics of Two Inline Tubes and Two Parallel Tubes[J]. Nuclear Power Engineering, 2014, 35(1): 87-91. |
[17] | Zhu Yong, Qin Jiaming, ReN Hongbing, Zuo Chaoping, Han Tongxing. Flow-Induced Vibration Analysis of Steam Generator Heat Transfer Tube Based on ANSYS[J]. Nuclear Power Engineering, 2014, 35(4): 17-20. doi: 10.13832/j.jnpe.2014.04.0017 |
[18] | JIANG Nai-bin, ZANG Feng-gang, ZHANG Yi-xiong, GUAN Hui. Research on Void Fraction Models for Vertically Upward Two-Phase Cross-Flow in Horizontal Tube Bundle[J]. Nuclear Power Engineering, 2013, 34(3): 67-70. |
[19] | QIAN Hao, XIE Yong-cheng, ZHANG Ke-feng. Preliminary Analysis of Flow Induced Vibration for AP1000 Secondary Core Support Assembly[J]. Nuclear Power Engineering, 2011, 32(S1): 145-148,158. |
[20] | LANG Hong-fang, YE Quan-liu, CHEN Fu-long. Discussion on Flow Induced Vibration Analysis Method for Shell-and-Tube Heat Exchanger with Nuclear Safety Class 2 and 3[J]. Nuclear Power Engineering, 2011, 32(S1): 155-158. |