[1] | Li Li, Zhang Yingxun, Yang Junping, Cui Ying, Chen Xiang, Wang Xinyu, Zhao Kai. Using Convolutional Neural Networks to Distinguish Nucleon Effective Mass Splitting[J]. Nuclear Power Engineering, 2025, 46(2): 68-75. doi: 10.13832/j.jnpe.2024.09.0028 |
[2] | Fan Haijun, Cui Hui, Wang Shanqiang, Wang Zungang, Zhou Hongzhao, Chen Wenzhuo, Tang Kaiyong. Dual-sided Trench Shaped Neutron Detector Using 6LiF/α-Al2O3:C Based on Optically Stimulated Luminescence[J]. Nuclear Power Engineering, 2024, 45(S1): 215-220. doi: 10.13832/j.jnpe.2024.S1.0215 |
[3] | Liu Dong, Tang Lei, An Ping, Zhang Bin, Jiang Yong. The Deep Learning Method to Search Effective Multiplication Factor of Nuclear Reactor Directly[J]. Nuclear Power Engineering, 2023, 44(5): 6-14. doi: 10.13832/j.jnpe.2023.05.0006 |
[4] | Wang Lipeng, Zhang Xinyi, Jiang Duoyu, Hu Tianliang, Cao Liangzhi, Wu Hongchun, Cao Lu. Evaluation of Thermal Neutron Scattering Data for H in ZrHx Based on Deterministic Method[J]. Nuclear Power Engineering, 2023, 44(5): 23-29. doi: 10.13832/j.jnpe.2023.05.0023 |
[5] | Zhu Wei, Hou Qinmai, Cai Ning, Xu Sai, Zhu Jie, Li Qiuqi. Analysis on Validity of Test Data of Primary Circuit Pressure Boundary Leakage Rate[J]. Nuclear Power Engineering, 2022, 43(6): 174-179. doi: 10.13832/j.jnpe.2022.06.0174 |
[6] | Cheng Xi, Zhou Guozheng, Tang Ximing, Liang Jun, Zhao Bowen. Effectiveness Assessment and Statistics of Eddy Current Signal in Measuring Oxide Layer of Fuel Rods[J]. Nuclear Power Engineering, 2020, 41(1): 49-53. doi: 10.13832/j.jnpe.2020.01.0049 |
[7] | Shen Dongming, Cai Jiantao, He Rui, Huang Xiaoming. Data Reliability Analysis during Containment Leakage Test Based on Statistical Software R[J]. Nuclear Power Engineering, 2020, 41(5): 99-103. |
[8] | Zhang Qi, Cao Guanghui, Geng Yan, Kong Jing, Liu Peng, Chen Zixi. Analysis of Effectiveness of Medium Voltage Mobile Power Supplies in M310 and Modified Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(4): 81-84. |
[9] | Wei Linfang, Wu Hongchun, Zheng Youqi, Du Xianan, Yuan Xianbao. Computational Method Study for Effective Self-Shielding Cross-Section of URR in Fast Reactor Code SARAX[J]. Nuclear Power Engineering, 2018, 39(S2): 38-42. doi: 10.13832/j.jnpe.2018.S2.0038 |
[10] | Wang Jia, Hu Zehua, Song Hongzhou, Ye Tao, Sun Weili. SIRIUS: A Code for Thermal Neutron Scattering Data Production for Solid Moderators[J]. Nuclear Power Engineering, 2018, 39(1): 34-37. doi: 10.13832/j.jnpe.2018.01.0034 |
[11] | Jiang Xialan, Liu Taili, Liu Yi, Zhang Xuan. Effectiveness Analysis for Core Coolant Monitoring System during Medium Loss of Coolant Accident[J]. Nuclear Power Engineering, 2017, 38(3): 115-118. doi: 10.13832/j.jnpe.2017.03.0115 |
[12] | Hu Tianliang, CAO Liangzhi, Wu Hongchun, ZHuang Kun. Calculation and Analysis of Effective Delayed Neutron Fraction βeff in MSR[J]. Nuclear Power Engineering, 2017, 38(S1): 37-40. doi: 10.13832/j.jnpe.2017.S1.0037 |
[13] | Jin Yue, Bao Han, Liu Xiaojing, Cheng Xu. Assessment of In-Vessel Retention for Advanced Large Size PWRs[J]. Nuclear Power Engineering, 2015, 36(3): 135-141. doi: 10.13832/j.jnpe.2015.03.0135 |
[14] | Shi Shaobo, Shen Ping, Tian Xianglu, Gao Luyang. Validity Analysis of Rolled Plugs of Steam Generators Tube[J]. Nuclear Power Engineering, 2015, 36(5): 72-74. doi: 10.13832/j.jnpe.2015.05.0072 |
[15] | Yin Qiang, Chai Xiaoming, Tu Xiaolan, Pan Junjie. Research of Simulation Program FRET for Fuel Rod Resonance Effective Temperature Mechanism[J]. Nuclear Power Engineering, 2014, 35(S2): 194-196. doi: 10.13832/j.jnpe.2014.S2.0194 |
[16] | WANG Lipeng, JIANG Xinbiao, ZHAO Zhumin, CHEN Lixin, LI Xuesong, XU Jiang, WU Hongchun. Calculation and Experimental Validation of 99Tc、129I Transmutation Rate in Xi’an Pulsed Reactor[J]. Nuclear Power Engineering, 2014, 35(2): 13-16. |
[17] | Yin Zhitao, LÜ Zheng, Wang Yulin, Zheng Wuqin. Research on Measurement of Neutron Flux in Irradiation Channels of Research Reactor[J]. Nuclear Power Engineering, 2014, 35(1): 117-121. |
[18] | Wang Jia, Song Hongzhou, Ye Tao, Hu Zehua, SuN Weili. Study on Thermal Neutron Scattering Data for ~7LiH[J]. Nuclear Power Engineering, 2014, 35(S2): 159-163. doi: 10.13832/j.jnpe.2014.S2.0159 |
[19] | YU Tao, QIAN Jindong, XIE Jinsen. Preliminary Design of LEU MNSR for BNCT with Excellent Epithermal Neutron Flux Treatment Beam[J]. Nuclear Power Engineering, 2012, 33(3): 17-20,37. |
[20] | CHEN Xing, ZHANG Shishun, LIN Jiming. Assessment of In-Vessel Corium Retention in CPR1000[J]. Nuclear Power Engineering, 2011, 32(3): 6-9,24. |