[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] | Li Haoxiang, Zheng Wei, Yin Huaqiang, Du Bin, Wang Qiuhao, He Xuedong, Ma Tao, Yang Xingtuan. Study on Decarburization and Oxidation Corrosion Behavior of T-22 Alloy in Impure Helium of High-temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2022, 43(4): 38-45. doi: 10.13832/j.jnpe.2022.04.0038 |
[4] | Jiang Zhuoer, Zhao Jun, WangHaitao, Shi Li, Wang Xiaoxin, Sun Weidong. Fragility Research for Storage Batteries of High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2020, 41(4): 105-110. |
[5] | Li Yinghong, Huang Hao, Zhou Rongsheng, Yang Xiaodong. Criticality Safety Calculation and Analysis of Fresh Fuel Element Transport Containers for High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2019, 40(6): 64-71. doi: 10.13832/j.jnpe.2019.06.0064 |
[6] | Gao Yingxian, Zhang Hang, Qiu Zhifang, Liu Zhaodong, Li Meifu, Zeng Wei. Research of ECCS Scheme for Small Modular PWR Based on Combination of Deterministic and Probabilistic Methods[J]. Nuclear Power Engineering, 2019, 40(3): 175-179. doi: 10.13832/j.jnpe.2019.03.0175 |
[7] | Jiang Zhuoer, Wang Haitao, Zhao Jun, Shi Li. Sensitivity Analysis for Seismic Fragilities of Lateral Supports of RPV for High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2018, 39(6): 53-58. doi: 10.13832/j.jnpe.2018.06.0053 |
[8] | Zhang Ruixiang, Zhao Feng, Peng Weichao, Yao Yao, Wang Zhen, Xu Haosong. Research on Controlling Method of Secondary Circuit Water Quality of High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2018, 39(5): 106-110. doi: 10.13832/j.jnpe.2018.05.0106 |
[9] | Qu Shen, Cao Liangzhi, Zhou Shengcheng, Liu Hangang. Study on Depletion Calculation of Heat Pipe Cooled Space Reactor[J]. Nuclear Power Engineering, 2018, 39(5): 4-8. doi: 10.13832/j.jnpe.2018.05.0004 |
[10] | 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 |
[11] | Wang Hongjie, SHi Li, Wang Xiaoxin, Sun Libin, Wu Xinxin. Study on Strength Distribution and Failure Probability for IG-110[J]. Nuclear Power Engineering, 2017, 38(3): 56-60. doi: 10.13832/j.jnpe.2017.03.0056 |
[12] | Bo Wen, Li Zhengcao, Wang Haitao, Shi Li. Research on Shape Optimization of RPV Opening of High Temperature Gas-Cooled Reactor Using Boundary Element Method[J]. Nuclear Power Engineering, 2016, 37(4): 24-27. doi: 10.13832/j.jnpe.2016.04.0024 |
[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] | 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. |
[17] | ZHOU Xiangwen, HAO Shaochang, ZHAO Xingyu, MA Jingtao, WANG Yang, DENG Zhangsheng. Wet Process of External Gelation of Uranium for Preparation of Uranium Dioxide Kernel of High Temperature Gas-cooled Reactors[J]. Nuclear Power Engineering, 2012, 33(4): 40-43. |
[18] | PENG Wei, YANG Xiaoyong, YU Suyuan, WANG Jie. Preliminary Analysis of Graphite Dust Motion in Helium Mainstream for HTR[J]. Nuclear Power Engineering, 2012, 33(5): 140-144. |
[19] | LI Xiaowei, ZHANG Li, WU Xinxin, HE Shuyan. Numerical Simulation of Flow Field in Cooling Tower of Passive Residual Heat Removal System of HTGR[J]. Nuclear Power Engineering, 2011, 32(3): 58-62,72. |
[20] | WANG Hai-tao, WU Xin-xin. Research on Creep and Fatigue Characteristics of MSIV at Elevated Temperature in HTR[J]. Nuclear Power Engineering, 2011, 32(S1): 18-21. |