[1] | Zhu Tenghao, Wang Hongtao, Wang Haitao. Research on Vibration-induced Noise Simulation of Main Control Room of High-temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(6): 132-138. doi: 10.13832/j.jnpe.2024.06.0132 |
[2] | Ni Man, Zhao Jun, Qian Hongtao, Zhang Jiajia, Gong Yu, Xiao Jun. Study on Risk-informed SSC Safety Classification of High Temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(3): 193-198. doi: 10.13832/j.jnpe.2024.03.0193 |
[3] | Liu Shuai, Zhou Yuan, Kang Mingming, Yuan Yuan, Du Zhengyu, He Xiaoqiang, Hu Wei. Experimental Study on Leakage of High Temperature Sodium Heat Pipe in the Air[J]. Nuclear Power Engineering, 2023, 44(6): 39-44. doi: 10.13832/j.jnpe.2023.06.0039 |
[4] | Tian Jun, Su Dongchuan, Li Hui, Xiong Furui, Liu Changjun, Bi Penghua, Tan Jianping. Mechanical Behavior Analysis of Heat Pipe Reactor Core Matrix Structure at High Temperature[J]. Nuclear Power Engineering, 2023, 44(1): 217-221. doi: 10.13832/j.jnpe.2023.01.0217 |
[5] | Yang Yang, Yang Yu, Chen Yunmin, Cao Qi, Xiong Wei, Lu Yunyun, Wu Xiaoyong. Theoretical Calculation of High Temperature Potential-pH Based on Fe-H2O, Cr-H2O and Zr-H2O Systems[J]. Nuclear Power Engineering, 2022, 43(1): 110-115. doi: 10.13832/j.jnpe.2022.01.0110 |
[6] | Jiang Tianze, Li Pengzhou, Ma Jianzhong, Gao Lixia, Zhang Xiaoling. Study on Flow Induced Vibration Characteristics of Laminated Plate Structure under High Temperature[J]. Nuclear Power Engineering, 2022, 43(S1): 132-136. doi: 10.13832/j.jnpe.2022.S1.0132 |
[7] | Zhang Jianxin, Gu Jipin, Chen Shuming, Pu Enshan, Guo Xiaoxian, Li Hailiang, Fang Jinghui. Fatigue Reliability Test and Evaluation of Main Pump Spindle of Nuclear Power Plant Reactor[J]. Nuclear Power Engineering, 2022, 43(2): 219-225. doi: 10.13832/j.jnpe.2022.02.0219 |
[8] | 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 |
[9] | Zhang Yi, Li Yan, Sun Bo, Cao Qifeng, Pan Junlin, Yang Xi, Yang Dezhen, Ren Yi. Fatigue Reliability Evaluation Method for Hold Down Spring of Reactor Vessel Internals Considering Stress Relaxation and Irradiation[J]. Nuclear Power Engineering, 2021, 42(6): 141-147. doi: 10.13832/j.jnpe.2021.06.0141 |
[10] | Zheng Liangang, Bai Xiaoming, Shi Kaikai, Du Juan. Effect of Main Bolt Break on Seal Performance, Stress and Fatigue of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2020, 41(5): 70-73. |
[11] | Zhang Xiaochun, Gong Wei. Structural Analysis and Evaluation Method for Nuclear Class 1 Piping Systems at Elevated Temperature[J]. Nuclear Power Engineering, 2019, 40(3): 198-204. doi: 10.13832/j.jnpe.2019.03.0198 |
[12] | Liu Yang, Wang Jun. Heat Transfer Simulation of Fuel Transport Cask for High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2017, 38(5): 160-163. doi: 10.13832/j.jnpe.2017.05.0160 |
[13] | Wang Yongfu, Sun Yuliang. Technical-Economic Study on High Temperature Reactor for Combined Heat and Power Generation[J]. Nuclear Power Engineering, 2016, 37(3): 181-184. doi: 10.13832/j.jnpe.2016.03.0181 |
[14] | Liu Dan, Sun Jun, Sun Yuliang. Dynamic Model and Analyses of Supercritical Steam Generator of High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2015, 36(2): 122-126. doi: 10.13832/j.jnpe.2015.02.0122 |
[15] | Luo Chending, Zhao Fuqiang, Zhou Jie, Zhang Na. Thermodynamic Analysis of High Temperature Gas-cooled Reactor He/Ammonia Combined Cycle[J]. Nuclear Power Engineering, 2014, 35(1): 165-169. |
[16] | ZhOu Zhou, Meng Shaopeng, Bao Jie. Study on Fatigue of Reactor Coolant Piping and Minimum Piping Wall Thickness[J]. Nuclear Power Engineering, 2014, 35(3): 46-50. doi: 10.13832/j.jnpe.2014.03.0046 |
[17] | YANG Wen, ZHANG Yixiong. Study on 3D Stress and Fatigue Analysis of RPV Nozzle Based on APDL[J]. Nuclear Power Engineering, 2013, 34(S1): 157-161. |
[18] | LI Gen, LIU Han-wei, REN Ping-di, ZHANG Xiao-yu. Study on Fretting Characteristics of Si3N4/NS315 Alloy at High Temperature[J]. Nuclear Power Engineering, 2013, 34(4): 171-175. |
[19] | ZHU Hongye, YANG Xingtuan, JU Huaiming, JIANG Shengyao. Analysis of Flow Excursion Instabilities in Helically Coiled Tube Steam Generator of High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2012, 33(4): 76-80. |
[20] | LEI Yue-bao, GAO Zeng-liang. Status and Development of R5 Procedure for Structural Integrity Assessment of High Temperature Components[J]. Nuclear Power Engineering, 2011, 32(S1): 9-12. |