[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] | 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 |
[3] | Xie Honghu, Zhang Feng, Liu Xiaohua, He Yingyong, Qin Junwei, Zhang Yihan. Assessment of Operating Characteristic of Equipment Access Hatch Lifting and Guiding Devices[J]. Nuclear Power Engineering, 2020, 41(1): 180-184. doi: 10.13832/j.jnpe.2020.01.0180 |
[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] | 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 |
[6] | Wang Dasheng, Liu Pan, JiN Ting, Lu Wenjie. Analysis and Discussion for Fast Fracture of Reactor Pressure Vessel (RPV) Based on RCC-M Code[J]. Nuclear Power Engineering, 2017, 38(5): 58-61. doi: 10.13832/j.jnpe.2017.05.0058 |
[7] | Zhao Wei. Calculation Method of Flange for RCC-M[J]. Nuclear Power Engineering, 2017, 38(2): 165-168. doi: 10.13832/j.jnpe.2017.02.0165 |
[8] | 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 |
[9] | 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 |
[10] | 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 |
[11] | Gu Jian, Li Jianli, Jiang Yu. Analysis of Suitability in Application of RCC-M[J]. Nuclear Power Engineering, 2015, 36(2): 119-121. doi: 10.13832/j.jnpe.2015.02.0119 |
[12] | 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 |
[13] | 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. |
[14] | YANG Wen-hua, TONG Ming-yan, SUN Sheng. Ansys CFX Thermal Analysis of Modular Tube-Type Irradiation Rig[J]. Nuclear Power Engineering, 2013, 34(4): 153-156. |
[15] | SHEN Yu-sheng, XIAO Jian. Limitations and Shortcomings of Duplex Stainless Steel Choice in RCC-M[J]. Nuclear Power Engineering, 2013, 34(5): 89-91,99. |
[16] | QI Huan-huan, CENG Zhong-xiu, ZHANG Yi-xiong, LIU Wen-jin, WANG Wei. Nonlinear Dynamic Analysis of LOCA Based on Secondary Development of ANSYS[J]. Nuclear Power Engineering, 2011, 32(S1): 98-102. |
[17] | LIN Song, ZHANG Kun, SUN Lei. Cross Mobility Computation of Supporting Structures for Pumps[J]. Nuclear Power Engineering, 2011, 32(S1): 152-154. |
[18] | LI Xing-hua, CAO Lei-sheng, NIE Lin-cheng. Analysis of Plastic Limit on Pipe Elbow under High Temperature and Pressure Based on ANSYS[J]. Nuclear Power Engineering, 2011, 32(S1): 120-124. |
[19] | ZHANG Qing-hong, LIU Pan, SHANG Er-tao. Stress Analysis of Reactor Pressure Vessel Support Rings[J]. Nuclear Power Engineering, 2011, 32(S1): 131-133. |
[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. |