[1] | Zhao Peng, Pan Ruian, Liu Zhen, Han Liangwen, Gao Yedong, Lai lisi, Sun Biao. Study on Method of Aging Management During Operation for High Flux Engineering Test Reactor[J]. Nuclear Power Engineering, 2023, 44(S1): 199-204. doi: 10.13832/j.jnpe.2023.S1.0199 |
[2] | Cai Wenchao, Li Songfa, Deng Yunli, Li Changxiang, Feng Haozhi, Qin Fujun, Lu Xing. Determination of Aging Management Scope for HFETR[J]. Nuclear Power Engineering, 2023, 44(S1): 217-222. doi: 10.13832/j.jnpe.2023.S1.0217 |
[3] | Li Songfa, Zhao Guang, Lyu Yunhe, Li Wenyu, Li Yun, Yan Xiongwei, Yao Liang. Technical Research and Practice of Aging Management Review for Research Reactor[J]. Nuclear Power Engineering, 2023, 44(S1): 205-210. doi: 10.13832/j.jnpe.2023.S1.0205 |
[4] | Kong Jing, Zhang Qi, Chen Zixi, Gao Xuan. Study on Aging Management Review of Electric and I&C Equipment in Evaluation of Nuclear Power Plant Operation License Extension[J]. Nuclear Power Engineering, 2022, 43(S1): 60-64. doi: 10.13832/j.jnpe.2022.S1.0060 |
[5] | Zhang Jiangtao, Wang Zhen, Chen Sen, Cai Dahua, Shi Wenxiang. Aging Review of Hydraulic Structures in Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(S1): 90-93. doi: 10.13832/j.jnpe.2022.S1.0090 |
[6] | Huang Chao, Xu Feng, Li Shiwei. Aging Evaluation of Baffle Bolts for Reactor Internals of Qinshan Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(S1): 16-21. doi: 10.13832/j.jnpe.2022.S1.0016 |
[7] | Zhao Xin, Cai Qi, Zhao Xinwen, Wang Xiaolong. Research on Fault Diagnosis of Nuclear Power System Based on Improved Linear Learning Algorithm[J]. Nuclear Power Engineering, 2020, 41(1): 134-139. doi: 10.13832/j.jnpe.2020.01.0134 |
[8] | Zhao Xin, Cai Qi, Zhang Liming, Zhao Xinwen, Wang Xiaolong, Li Haicui. Research on Evaluation Method of Nuclear Power Pipeline Fracture Size under Random Missing Data[J]. Nuclear Power Engineering, 2020, 41(6): 187-193. |
[9] | Jiang Botao, Huang Xinbo, Hines J.Wesley, Zhao Fuyu. Prediction of Reactor Power under Accident Conditions of Nuclear Power Plant Using ν-Support Vector Machine[J]. Nuclear Power Engineering, 2019, 40(6): 105-108. doi: 10.13832/j.jnpe.2019.06.0105 |
[10] | Jiang Botao, Hines J. Wesley, Zhao Fuyu. Application of Ant Colony Optimization Least Squares Support Vector Machine in Measurement Data Fitting[J]. Nuclear Power Engineering, 2018, 39(6): 156-160. doi: 10.13832/j.jnpe.2018.06.0156 |
[11] | Huang Junlin, Liu Xianghong, Huang Bingyan. Evaluation of Thermal Ageing of RCP 90° Elbow for Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(2): 105-108. doi: 10.13832/j.jnpe.2015.02.0105 |
[12] | Liu Songya, Zhao Xuecen, Liu Lizhi, Deng Liping. Study on Separating Speed of Cam Anti-Reverse Device In Shield Pump[J]. Nuclear Power Engineering, 2015, 36(S2): 37-40. doi: 10.13832/j.jnpe.2015.S2.0037 |
[13] | ZHANG Xiaomei, JIA Yaqing, LIU Peng, CHEN Qibing, LI Ziyan, ZHANG Ying. Research on HFETR Ageing Management and HFETR Ageing Management Database System Development[J]. Nuclear Power Engineering, 2014, 35(2): 166-169. |
[14] | Yuan Can, Cai Qi, Guo Li, Yan Feng. Prediction about Chaotic Times Series of Natural Circulation Flow under Rolling Motion[J]. Nuclear Power Engineering, 2014, 35(1): 60-63. |
[15] | ZHANG Sheng, MA Yi-jin, JIANG Hong, CHEN Shi-jun, HUANG Li-jun, MO Chun-ni. Analysis and Management of Accelerated Aging of Relay in NPPs[J]. Nuclear Power Engineering, 2013, 34(2): 129-132. |
[16] | REN Shu-hong, XUE Fei, YU Weiwei, TI Wen-xin, LIU Xiao-tian. Reliability Residual-Life Prediction Method for Thermal Aging Based on Performance Degradation[J]. Nuclear Power Engineering, 2013, 34(5): 96-99. |
[17] | LUO Qiang, XU Qi, ZHAO Jisong, REN Liping, CHEN Yong, MA Na. Aging Management of Reactor Pressure Vessel for PWR Nuclear Power Plants[J]. Nuclear Power Engineering, 2012, 33(S2): 114-119. |
[18] | YUE Xia, ZHANG Chunliang, QUAN Yanming, ZHU Houyao. Fault Diagnosis of Nuclear-Powered Equipment Based on HMM&SVM[J]. Nuclear Power Engineering, 2012, 33(3): 104-108. |
[19] | WANG Zhaoxi, XUE Fei, GONG Mingxiang, TI Wenxin, LIN Lei, LIU Peng. Evaluation of Vibration and Vibration Fatigue Life for Small Bore Pipe in Nuclear Power Plants[J]. Nuclear Power Engineering, 2011, 32(2): 39-43. |
[20] | SHI Chunsheng, MENG Dapeng. Combined Prediction Model for Supply Risk in Nuclear Power Equipment Manufacturing Industry Based on Support Vector Machine and Decision Tree[J]. Nuclear Power Engineering, 2011, 32(5): 138-142. |