[1] | Min Guangyun, Jiang Naibin. A Reduced-Order Model of Mode Characteristics and Flow-Induced Vibration Response of Fuel Rod Based on POD Method[J]. Nuclear Power Engineering, 2024, 45(4): 142-149. doi: 10.13832/j.jnpe.2024.04.0142 |
[2] | Ma Zhengqing, Pang Hua, Zhang Kun, Tang Changbing, Wu Zhouzhi, Yan Feng, Xing Shuo. Three Dimensionnal Simulation Investigation of Wedged Pellet-Clad Interaction Problem in Fuel Rod[J]. Nuclear Power Engineering, 2023, 44(S2): 6-10. doi: 10.13832/j.jnpe.2023.S2.0006 |
[3] | Li Xiangdong, Jiang Hesong, Wang Xueyuan, Xu Xuejin, He Xiaochun. Research on Automatic Calibration Algorithm of Reactor Fuel Rods[J]. Nuclear Power Engineering, 2023, 44(4): 203-208. doi: 10.13832/j.jnpe.2023.04.0203 |
[4] | Li Weicai, Liu Pengliang, Wang Congzheng, Guo Yan. Research on Machine Vision Measurement Method of Rod Spacing Data for PWR Fuel after Irradiation[J]. Nuclear Power Engineering, 2022, 43(4): 53-59. doi: 10.13832/j.jnpe.2022.04.0053 |
[5] | Li Wenjie, Qi Feipeng, Sun Dan, Xin Yong, Li Quan, Li Yuanming. Research on Percolation Models of UO2 Fission Gas Release[J]. Nuclear Power Engineering, 2022, 43(3): 226-231. doi: 10.13832/j.jnpe.2022.03.0226 |
[6] | Wu Dan, Deng Jian, Ding Shuhua, Xin Sufang, Xian Lin, Bi Shumao, Mao Huihui. Effect of Rod Swelling and Rupture on LOCA Process[J]. Nuclear Power Engineering, 2020, 41(3): 188-192. doi: 10.13832/j.jnpe.2020.03.0188 |
[7] | Li Chenyue, Dong Bing, Yin Junlian, Li Leihao, Wang Dezhong. Computational Simulation Research of Unstable Mechanics of Fission Gas Release under Condition of Fuel Cladding Breach[J]. Nuclear Power Engineering, 2020, 41(3): 97-103. doi: 10.13832/j.jnpe.2020.03.0097 |
[8] | Chen Hongsheng, Long Chongsheng, Xiao Hongxing, Wei Tianguo, Gao Wen. Releasing Model of Fission Gas Based on Dispersion Fuel Particle Cracking[J]. Nuclear Power Engineering, 2019, 40(5): 85-91. |
[9] | Qi Huanhuan, Feng Zhipeng, Jiang Naibin, Huang Qian, Wu Wanjun, Huang Xuan, Jiang Xiaozhou. Numerical Study on Effect of Clamping Failure on Flow Induced Vibration and Fretting Wear Analysis of Fuel Rods[J]. Nuclear Power Engineering, 2018, 39(4): 182-186. doi: 10.13832/j.jnpe.2018.04.0182 |
[10] | Huang Fan, Deng Changyi, Yang Tonggao, You Yong, Chen Lei. Design Research of Equipment for Pressing Bottom End Plug of Fuel Rods[J]. Nuclear Power Engineering, 2017, 38(S1): 4-7. doi: 10.13832/j.jnpe.2017.S1.0004 |
[11] | Tang Changbing, Chen Ping, Zhou Yi, Chen Liang, Li Wei, Wang Lu. Simulation Investigation of Thermal-Mechanical Behaviors of MPS Defect Fuel Rod[J]. Nuclear Power Engineering, 2017, 38(6): 36-41. doi: 10.13832/j.jnpe.2017.06.0036 |
[12] | Li Hang, Zhou Qi, Zhu Qingfu. Modeling Method for Random Arrays of Rod in Spent Fuel Dissolver[J]. Nuclear Power Engineering, 2017, 38(1): 29-31. doi: 10.13832/j.jnpe.2017.01.0029 |
[13] | Jiang Xiaochuan, Song Zifan, He Kai, Yang Nirong. Uncertainty Analysis of Manufacturer Parameters Impact on TVS-2M Fuel Rod Performance in Reactor[J]. Nuclear Power Engineering, 2017, 38(4): 134-138. doi: 10.13832/j.jnpe.2017.04.0134 |
[14] | Guo Xingkun, Tian Haowen, Zhou Yi, Zhang Minjie, Li Songling, Liu Songtao. Study on Corrosion and Hydriding Performance and Model of Specifically Fuel Rod Cladding[J]. Nuclear Power Engineering, 2016, 37(S1): 9-11. doi: 10.13832/j.jnpe.2016.S1.0009 |
[15] | 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 |
[16] | Zhou Yi, Chen Ping, Zhang Lin, Li Wenjie, XinG Shuo, Guo Xingkun, Liu Zhenhai, Tu Xiaolan. Modeling of PWR Fuel Rod Irradiation Behaviour[J]. Nuclear Power Engineering, 2014, 35(S2): 200-202. doi: 10.13832/j.jnpe.2014.S2.0200 |
[17] | RU Jun, XIAO Zhong, PU Zeng-ping, YONG Jing, HUANG Chun-lan, GU Ming-fei, SU Min. Modeling Research on PWR Fuel Assembly Lateral Non-linear Characteristics[J]. Nuclear Power Engineering, 2013, 34(6): 48-51. |
[18] | XING Shuo, YAO Dong, YIN Chun-yu, PANG Hua, TU Xiao-lan. Preliminary Study on SCWR Fuel Rod Performance Analysis Code[J]. Nuclear Power Engineering, 2013, 34(1): 97-100,120. |
[19] | HAO Yalei, YANG Xingtuan, JIANG Shengyao, LIU Zhiyong. Thermal Strain of Fuel Rods during Transient of Operation Transformation[J]. Nuclear Power Engineering, 2012, 33(1): 78-82. |
[20] | CUI Yi, DING Shurong, ZHAO Yunmei, HUO Yongzhong, WANG Canglong, YANG Lei. Fission Gas Model for UO2 Fuels Considering Bubble Coalescence and Grain Boundary Diffusion[J]. Nuclear Power Engineering, 2012, 33(S2): 9-12,42. |