[1] | Zhao Ziyan, Xiang Zhaocai, Zhao Pengcheng. Research on Fast Prediction Method of Neutron Flux Based on Hybrid Driven Reduced Order Model[J]. Nuclear Power Engineering, 2024, 45(4): 1-8. doi: 10.13832/j.jnpe.2024.04.0001 |
[2] | 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 |
[3] | Zhang Sifan, Yuan Yuan, Liu Zhouyu, Zhou Xinyu, Cao Liangzhi. A Two-dimensional Coupled Neutron Transport Method for MOC and SN via Boundary Fluence Rate Coupling[J]. Nuclear Power Engineering, 2022, 43(2): 9-16. doi: 10.13832/j.jnpe.2022.02.0009 |
[4] | Wang Wenhui, Wan Anping, Deng Chaojun, Gong Zhipeng, Zhang Hongliang, Ye Yanghan, Wang Pengfei, Liu Canxian, Li Yuezhang. Reliability Evaluation Method of Bolts of Reactor Internals in High-neutron-fluence-rate Region Based on XGBoost[J]. Nuclear Power Engineering, 2022, 43(5): 154-162. doi: 10.13832/j.jnpe.2022.05.0154 |
[5] | Ma Xiaoyu, Deng Tao. Improvement and Test Verification of Reactor-Core Neutron and Temperature Detector[J]. Nuclear Power Engineering, 2021, 42(2): 105-109. doi: 10.13832/j.jnpe.2021.02.0105 |
[6] | Zou Peng, Cao Jiebao, Wang Yunbo, Tang Xiding, Kang Changhu, Yang Bin. Effect of Spectrum Variation on Activation Measurement for Neutron Fluence[J]. Nuclear Power Engineering, 2019, 40(4): 56-59. |
[7] | 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 |
[8] | Zhang Mingqian, Huang Meiliang, Fu Yueming, Chu Qianqian. Assessment on Wear of In-Core Flux Thimble in a Typical Pressurized Water Reactor[J]. Nuclear Power Engineering, 2018, 39(6): 96-100. doi: 10.13832/j.jnpe.2018.06.0096 |
[9] | Ma Liyong, Xiang Yuxin, Wang Hao, ZHang Ping, CAO Jiebao. Demonstration Experiment for Graphite Material Irradiation in HFETR[J]. Nuclear Power Engineering, 2017, 38(S1): 157-159. doi: 10.13832/j.jnpe.2017.S1.0157 |
[10] | Wang Hao, Xiang Yuxin, Xu Taozhong, ZHang Ping, ZHu Lei. Verification of Neutron Flux Calculation Method for HFETR[J]. Nuclear Power Engineering, 2017, 38(S1): 154-156. doi: 10.13832/j.jnpe.2017.S1.0154 |
[11] | XiE Jinsen, Chen Zhenping, Yu Tao, XiE Qin, Zeng Wenjie, Liu Zijing, HE Lihua. Theoretical Study of Steady State Neutron Flux Density Re-Construction in ADS by Using Higher-Order Modes[J]. Nuclear Power Engineering, 2017, 38(6): 27-30. doi: 10.13832/j.jnpe.2017.06.0027 |
[12] | Liu Hongqian, Liu Shuiqing, Xiang Yuxin, Wang Hao, MA Liyong. Research of Material Irradiation Fine Neutron Flux Spectrum in HFETR[J]. Nuclear Power Engineering, 2017, 38(1): 10-12. doi: 10.13832/j.jnpe.2017.01.0010 |
[13] | 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. |
[14] | ZhenG Zheng, Wu Hongchun, Cao Liangzhi, Mei Qiliang, Li Hui. Application of Three-Dimensional Discrete Ordinatesand Monte Carlo Coupling Method on Fast Neutron Fluence Rate Calculation[J]. Nuclear Power Engineering, 2014, 35(S2): 60-63. doi: 10.13832/j.jnpe.2014.S2.0060 |
[15] | 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 |
[16] | Zhao Xiuliang, Huang Shun, Liu Liyan, Liu Caixue, ZoNG Xuncheng. Measurement Device for Multi-Channel Neutron Flux Relative Distribution[J]. Nuclear Power Engineering, 2014, 35(4): 82-85. doi: 10.13832/j.jnpe.2014.04.0082 |
[17] | DENG Lilin, LU: Huanwen, TAN Yi, XIAO Feng, WEI Shuping. Research on Theoretical Calculation Method for Refined Modeling of Fast Neutron Flux in Irradiation Surveillance Capsule[J]. Nuclear Power Engineering, 2013, 34(S1): 84-86. |
[18] | 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. |
[19] | ZHANG Ying, CHEN Zhi, WANG Shu, SUN Jian. Simulation Study on Correction Factor for Changing of Power Range Neutron Flux Rate of NPP Nuclear Instrumentation System[J]. Nuclear Power Engineering, 2012, 33(6): 42-45,60. |
[20] | LI Gaofeng, LIU Caixue, LAI Wanchang, MU Keliang. Calculation of Lead Shielding in Relative Distribution Measurement Systems of Neutron Flux in Reactors[J]. Nuclear Power Engineering, 2012, 33(4): 34-36. |