[1] | Hou Jiru, Liu Shifeng. Research of Ultimate Load Characteristics of Hoisting Structure Carrier for Equipment Hatch[J]. Nuclear Power Engineering, 2024, 45(2): 199-202. doi: 10.13832/j.jnpe.2024.02.0199 |
[2] | Liu Haoran, Lu Yeming, Wang Xiaofang, Li Jialing, Zhang Zhigang. Study on the Influence of Bionic Guide Vane on the Performance of CAP1400 Main Pump[J]. Nuclear Power Engineering, 2023, 44(2): 77-83. doi: 10.13832/j.jnpe.2023.02.0077 |
[3] | Guo Shuwei, Chen ZhenPing, Jiang Xinbiao, Li Da, Zhang Xinyi, Wang Lipeng, Hu Tianliang, Xie Jinsen, Yu Tao. Study on Neutronic/Thermal-Mechanical Coupling Calculation Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel[J]. Nuclear Power Engineering, 2022, 43(4): 31-37. doi: 10.13832/j.jnpe.2022.04.0031 |
[4] | Jiang Shenghan, Fan Kai, Wang Yongchao, Wang Shuai, Zhang Kun. Application Study of Cloud Computing in Stress Analysis and Optimization Design of Nuclear Pipe[J]. Nuclear Power Engineering, 2021, 42(S2): 150-153. doi: 10.13832/j.jnpe.2021.S2.0150 |
[5] | He Yingyong, Li Qiang, Xie Honghu, Zhang Feng, Liu Xiaohua. Optimization of Transmission Gear of Personnel Airlock for In-Service Nuclear Power Plant[J]. Nuclear Power Engineering, 2020, 41(6): 96-100. |
[6] | 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. |
[7] | Wang Di, Xiong Meng, Wu Shaowei. Study on Planeness Deviation of Bottom Steel Liner in Nuclear Power Plant Containment during Construction[J]. Nuclear Power Engineering, 2018, 39(S1): 122-124. doi: 10.13832/j.jnpe.2018.S1.0122 |
[8] | Ning Qingkun, Bai Xujuan. Calculation of Mixed Nuclear Piping Model with Elbow[J]. Nuclear Power Engineering, 2018, 39(S1): 119-121. doi: 10.13832/j.jnpe.2018.S1.0119 |
[9] | Zhang Qingyang, Gu Long, Peng Tianji, Sheng Xin. Safety Analysis of CiADS Sub-Critical Reactor Fuel Cladding under Beam Transients[J]. Nuclear Power Engineering, 2018, 39(5): 51-57. doi: 10.13832/j.jnpe.2018.05.0051 |
[10] | Qi Huanhuan, Wu Wanjun, Shen Pingchuan, Jiang Naibin, Ye Xianhui, Huang Xuan, Huang Qian. Dynamic Analysis of Fuel Assembly for Accident Condition Based on ANSYS[J]. Nuclear Power Engineering, 2018, 39(3): 40-44. doi: 10.13832/j.jnpe.2018.03.0040 |
[11] | ZHENG Liangang, XIE Hai, SU Dongchuan, SHAO Xuejiao. Study of Reactor Pressure Vessel Fatigue Crack Growth Analysis Based on ANSYS[J]. Nuclear Power Engineering, 2015, 36(6): 67-69. doi: 10.13832/j.jnpe.2015.06.0067 |
[12] | Wang Yanping, Peng Xingming, Tang Yujian. Application of Multi-Point Response Spectrum Method in Seismic Analysis of Nuclear Power Equipment[J]. Nuclear Power Engineering, 2015, 36(5): 54-56. doi: 10.13832/j.jnpe.2015.05.0054 |
[13] | XIe Hai, Gao Shiqing, ZHeng Liangang, Ceng Zhongxiu. Application of ANSYS User Subroutine in Thermal Transient Analysis[J]. Nuclear Power Engineering, 2015, 36(S2): 127-130. doi: 10.13832/j.jnpe.2015.S2.0127 |
[14] | 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 |
[15] | LI Zhongcheng, FAN Hong. Dynamic Impedance Analysis Based on an Artificial Viscoelastic Boundary Technology for Nuclear Power Engineering[J]. Nuclear Power Engineering, 2014, 35(2): 67-70. |
[16] | LIU Pan, JIN Ting, MAO Qing. Analysis on Fatigue Strength Reduction Factor of Reactor Pressure Vessel Flange Thread[J]. Nuclear Power Engineering, 2011, 32(S2): 9-12. |
[17] | XU Yu, DONG Jian-ling. Study on Simplified Stress Analysis Model of Steam Generator Tube in 10 MW High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2011, 32(S1): 61-64. |
[18] | LI Hai-long, GAO Fu-hai, LI Nan. Stress Analysis and Evaluation of Heavy Double-Hole Pipe Clip[J]. Nuclear Power Engineering, 2011, 32(S1): 117-119. |
[19] | DU Kun, WU Gao-feng. Strength Analysis for Equipment Gate of Nuclear Power Plants[J]. Nuclear Power Engineering, 2011, 32(S1): 110-112. |
[20] | LIAO Kuai, LI Peng-zhou, CHEN Xue-de. Study on Assessment Method for Typical Plate and Shell-Support in Nuclear Power Plants[J]. Nuclear Power Engineering, 2011, 32(S1): 103-106. |