[1] | Li Liangxing, Xu Xiangyang, Xiang Zutao, Shi Shang, Lei Zhenxin. Investigation on the Flow and Heat Transfer Characteristics of Liquid Lead Cross-flow Tube Bundle under Cooling Conditions[J]. Nuclear Power Engineering, 2025, 46(1): 116-127. doi: 10.13832/j.jnpe.2025.01.0116 |
[2] | Wang Ningyuan, Chen Deqi, Liu Hanzhou, Bu Shanshan. Experimental Study on Single-phase Flow-induced Vibration Mechanism in Helical Coiled Tubes[J]. Nuclear Power Engineering, 2024, 45(S2): 174-179. doi: 10.13832/j.jnpe.2024.S2.0174 |
[3] | Li Liangxing, Shi Shang, Zhao Haoxiang, Zhao Jiayuan. Design and Multi-Objective Optimization Study of Liquid Lead-Supercritical Carbon Dioxide Heat Exchanger[J]. Nuclear Power Engineering, 2024, 45(4): 196-204. doi: 10.13832/j.jnpe.2024.04.0196 |
[4] | Tang Hairong, Li Ying, Lou Ruifan, Yue Nina, Wang Suhao, Wang Sheng. Research on Impurity Regulation and Purification Technology of Liquid Lead-based Metal Coolant[J]. Nuclear Power Engineering, 2024, 45(S2): 274-278. doi: 10.13832/j.jnpe.2024.S2.0274 |
[5] | Guo Xiaoxian, Gu Jipin, Zhu Hao, Liu Yang, Li Taifeng, Zhang Hu. Study on the Operation Characteristics of the Primary Main Circulating Pump of Sodium-cooled Fast Reactor under the Switching Condition of Off-site Main and Auxiliary Power Supplies[J]. Nuclear Power Engineering, 2023, 44(1): 104-108. doi: 10.13832/j.jnpe.2023.01.0104 |
[6] | Xia Bangyang, Xu Can, Qin Tianjiao, Li Qing. Study on Loading Pattern for Long-cycle Lead-cooled Fast Reactor Core[J]. Nuclear Power Engineering, 2023, 44(6): 260-265. doi: 10.13832/j.jnpe.2023.06.0260 |
[7] | Liu Guixiu, Yi Jingwei, Li Gen, Liang Tiebo, Fang Huawei, Chen Weixiong. Study on Control Strategy of Natural Circulation Lead-cooled Fast Reactor Coupled with S-CO2 Brayton Cycle[J]. Nuclear Power Engineering, 2023, 44(4): 138-147. doi: 10.13832/j.jnpe.2023.04.0138 |
[8] | Sun Aodi, Sun Peiwei, Wei Xinyu. Study on Core Power Control of Small Lead-Bismuth Cooled Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(6): 155-161. doi: 10.13832/j.jnpe.2022.06.0155 |
[9] | Zhang Wei, Li Jingsong, Shi Huilie, Qiao Pengrui, Wang Cong, Zhang Tianqing, He Yingzhao. Thermal-Hydraulic Performance Analysis of Horizontal Spiral Tube Steam Generator for European Lead-Cooled Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(3): 38-45. doi: 10.13832/j.jnpe.2022.03.0038 |
[10] | Fu Peng, Liu Bing, Zhang Xinying. Study on the Effect of MA Nuclides Transmutation on Safety in Lead-Cooled Fast Reactors[J]. Nuclear Power Engineering, 2021, 42(5): 71-75. doi: 10.13832/j.jnpe.2021.05.0071 |
[11] | Zhao Ningning, Yuan Hongsheng, Wen Qinglong, Ruan Shenhui. Evaluation of the Impact of Core Power Distribution on Reflooding Phenomenon in CCTF Test[J]. Nuclear Power Engineering, 2021, 42(6): 58-64. doi: 10.13832/j.jnpe.2021.06.0058 |
[12] | Jiang Qingfeng, Zeng Wenjie. Development and Application of Fuzzy Switching Control System for Nuclear Reactor Core[J]. Nuclear Power Engineering, 2021, 42(2): 110-114. doi: 10.13832/j.jnpe.2021.02.0110 |
[13] | Jiang Qingfeng, Xie Jinsen, Zeng Wenjie, Chen Lezhi. Fuzzy-PID Control for Core Power of Liquid Molten Salt Reactor[J]. Nuclear Power Engineering, 2020, 41(1): 93-98. doi: 10.13832/j.jnpe.2020.01.0093 |
[14] | Jiang Qingfeng, Zeng Wenjie, Yu Tao, Xie Jinsen, Chen Lezhi. Core Power Control of Liquid Molten Salt Reactor Based on Variable Universe Fuzzy-PID[J]. Nuclear Power Engineering, 2020, 41(2): 109-113. |
[15] | Pan Yuekai, Qian Hong, Jiang cheng, Liu Xiaojing. Adaptive Predictive Control for Core Power Based on CPSO Rolling Optimization[J]. Nuclear Power Engineering, 2020, 41(6): 143-149. |
[16] | Pan Yuekai, Qian Hong, Jiang Cheng, Liu Xiaojing. Application of Generalized Predictive Control in Reactor Core Variable Power Control[J]. Nuclear Power Engineering, 2020, 41(2): 96-101. |
[17] | Du Shangmian, Zeng Wenjie, Yu Tao, Chen Lezhi, Xie Jinsen. Study on Power Control of Liquid Molten Salt Reactor Based on Core Linearization Model[J]. Nuclear Power Engineering, 2019, 40(6): 109-113. doi: 10.13832/j.jnpe.2019.06.0109 |
[18] | Shi Kangli, Zhang Xilin, Chen Hongli. Transient Analysis on Overpower and Loss of Heat Sink of A Small Natural Circulation Lead-Cooled Fast Reactor[J]. Nuclear Power Engineering, 2017, 38(4): 1-5. doi: 10.13832/j.jnpe.2017.04.0001 |
[19] | LIAO Long-tao, CHEN Zhi. Study on Nuclear Reactor Power Control Based on T-S Neuro-Fuzzy Network[J]. Nuclear Power Engineering, 2013, 34(3): 109-112. |
[20] | CHEN Zhi, LIAO Longtao, LIU Lixin, LI Wei. Study on Application of T-S Fuzzy Neural Method in Once Through Steam Generator Feedwater Control[J]. Nuclear Power Engineering, 2012, 33(4): 20-23,33. |