[1] | Jin Yuan, Gu Chenglong, Tian Wei, Zhang Yuxiang, Li Weicai. Analysis and Research on Axial Stiffness Model and Influencing Factors of PWR Fuel Assembly[J]. Nuclear Power Engineering, 2024, 45(6): 112-120. doi: 10.13832/j.jnpe.2024.06.0112 |
[2] | Guo Yan, Zhang Guoliang, Liu Huan, Li Weicai. Simulation Research on Additional Mass of PWR Fuel Assembly[J]. Nuclear Power Engineering, 2023, 44(2): 129-135. doi: 10.13832/j.jnpe.2023.02.0129 |
[3] | Guo Yan, Zhang Guoliang, Zhang Yanhong, Li Weicai, Hu Xiao, Gu Chenglong. Study on Seismic Test of PWR Fuel Assembly[J]. Nuclear Power Engineering, 2023, 44(2): 109-115. doi: 10.13832/j.jnpe.2023.02.0109 |
[4] | Li Fan, Liu Zhouyu, Wang Xining, Cao Liangzhi, Wu Hongchun. High-fidelity Full Core Neutronics Calculation Method for Fuel Assembly Bowing and Its Application[J]. Nuclear Power Engineering, 2023, 44(4): 9-16. doi: 10.13832/j.jnpe.2023.04.0009 |
[5] | Qu Shen, Cao Qixiang, Wu Xinghua, Yin Miao, Zhao Fengchao, Wang Xueren, Duan Xuru, Wang Xiaoyu. Method Study and Application for Neutronics Optimization of Solid Tritium Breeding Blanket of Fusion Reactor[J]. Nuclear Power Engineering, 2022, 43(S2): 143-149. doi: 10.13832/j.jnpe.2022.S2.0143 |
[6] | Huang Xing, Wan Chenghui, Li Yunzhao, Wu Hongchun, Gu Weiquan, Cai Guangming, Xu Jialong. Neutronics Influence Research on Axial Grid of PWR Fuel Assembly[J]. Nuclear Power Engineering, 2022, 43(1): 52-56. doi: 10.13832/j.jnpe.2022.01.0052 |
[7] | Zheng Yong, Lu Wei, Ma Yongqiang, Cui Xiantao, Guo Fengcheng, Ma Dangwei, Tu Xiaolan. Study on CUDA-based Heterogeneous Parallel for Advanced Assembly Neutronics Program[J]. Nuclear Power Engineering, 2021, 42(S2): 124-129. doi: 10.13832/j.jnpe.2021.S2.0124 |
[8] | Zhang Chenglong, Du Shuhong, Liu Guoming, HuoXiaodong, Yang Haifeng, Shao Zeng. Research on Neutronics Characteristics of Small Modular Super-Safe Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2019, 40(6): 13-19. doi: 10.13832/j.jnpe.2019.06.00013 |
[9] | Chen Boquan, Peng Qian, Hong Xiaofeng, Liu Ranchao, Qiu Shaoyu, Xie Huaiying, Chen Le. Effect of Hydride Orientation on Tensile and Bursting Properties of Zr-4 Cladding Tubes at Room Temperature[J]. Nuclear Power Engineering, 2019, 40(1): 60-64. doi: 10.13832/j.jnpe.2019.01.0060 |
[10] | Chen Boquan, Peng Qian, Zeng Zihan, Zhao Suqiong, Hong Xiaofeng, Qiu Shaoyu, Xu Chunrong. Research on Preparation Method for Zr-4 Tubes with Different Hydride Orientation[J]. Nuclear Power Engineering, 2019, 40(1): 51-55. doi: 10.13832/j.jnpe.2019.01.0051 |
[11] | Ming Pingzhou, Li Zhigang, An Ping, Xia Bangyang, Lu Wei, Liu Dong, Yu Hongxing. Automatic Contrast Verification of DRAGON and Core Neutronics Software Developed on Self-Reliance[J]. Nuclear Power Engineering, 2018, 39(S1): 5-9. doi: 10.13832/j.jnpe.2018.S1.0005 |
[12] | Peng Jinghan. Effects of Dual-Enrichment Fuel Management on Neutronic Data in Reactor Core[J]. Nuclear Power Engineering, 2018, 39(S2): 62-66. doi: 10.13832/j.jnpe.2018.S2.0062 |
[13] | Ru Jun, Xiao Zhong, Zhu Fawen, Zhang Lin, Qin Mian, Liu Yanghua. Analysis of Measures for Safe Operation of PWR Fuel Assemblies[J]. Nuclear Power Engineering, 2017, 38(6): 175-179. doi: 10.13832/j.jnpe.2017.06.0175 |
[14] | CHEN Le, XIE Meng, PEI Qilin, DAI Xun, XU Chunrong. Reliability of Test and Measurement for Hydride Reorientation[J]. Nuclear Power Engineering, 2015, 36(1): 55-59. doi: 10.13832/j.jnpe.2015.01.0055 |
[15] | Zhang Min, Cao Fangfang, Que Ji. Study on Measurement Method of 235U Isotope Abundance of Fuel Assembly for Research Reactor Based on a Compact Neutron Generator[J]. Nuclear Power Engineering, 2014, 35(4): 10-12. doi: 10.13832/j.jnpe.2014.04.0010 |
[16] | Yuan Xianbao, Cao Liangzhi. Analysis of Neutronics Characteristics of Small Modular Pb-Bi Cooled Reactor Core with Nitride Fuel[J]. Nuclear Power Engineering, 2014, 35(S2): 38-40. doi: 10.13832/j.jnpe.2014.S2.0038 |
[17] | Xia Bing, Li Fu, Wei Chunlin, Chen Fubing, Xu Xiaolin, Jing Yingqing. Neutronics and Accident Analysis of Th-U-MOX Loading in Pebble Bed High-temperature Reactors[J]. Nuclear Power Engineering, 2014, 35(S2): 31-33. doi: 10.13832/j.jnpe.2014.S2.0031 |
[18] | CHAI Xiaoming, MA Yongqiang, WANG Yuwei, LU Wei, YAO Dong. Development and V&V of Advanced Neutronics Code System SARCS-4.0[J]. Nuclear Power Engineering, 2013, 34(S1): 24-26. |
[19] | SHI Xueming, PENG Xianjue. Effect of Volume Ratio between Uranium and Water on Fusion-Fission Hybrid for Energy Production[J]. Nuclear Power Engineering, 2012, 33(4): 139-142. |
[20] | MA Xubo, CHEN Yixue, QUAN Guoping, WANG Yue, HAN Jingru, LU Daogang. Neutronics Calculation of Fusion-Fission Hybrid Breeding Thorium Fuel Assembly[J]. Nuclear Power Engineering, 2012, 33(1): 129-133. |