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[2] | Yuan Qingqing, Li Xiaobo, Zhang Zhenghao, Cheng Changming, Zhang Xiaojie, Ye Xinnan, Wang Wei. Experimental Study on Plasma High Temperature Melting Treatment Process[J]. Nuclear Power Engineering, 2024, 45(S1): 203-207. doi: 10.13832/j.jnpe.2024.S1.0203 |
[3] | Huang Qianming, Li Lan, Chai Xiaoming, Liu Bin, Ying Dongchuan. Selection of Shadow Shielding Structure and Material for Space Reactor[J]. Nuclear Power Engineering, 2023, 44(4): 17-24. doi: 10.13832/j.jnpe.2023.04.0017 |
[4] | Luo Fengyan, Li Wenqiang, Zhang Qingyu, Wang Guohua, Guo Jinxuan. Determination of Trace Arsenic, Plumbum, Stannum and Stibium in Nickel-Based Alloys by Inductively Coupled Plasma Mass Spectrometry[J]. Nuclear Power Engineering, 2023, 44(S2): 211-215. doi: 10.13832/j.jnpe.2023.S2.0211 |
[5] | Guo Qingyang, Zhang Jingyu, Zhang Huijie, Wang Qingbin. Calculation of Source Terms for Water-cooled Fusion Reactor Based on Deviation Effect Nuclide Screening Method[J]. Nuclear Power Engineering, 2022, 43(5): 1-6. doi: 10.13832/j.jnpe.2022.05.0001 |
[6] | 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 |
[7] | Xiao Xiang, Wu Jun, Chen Yixue, Yang Tongrui, Zhu Chenglin, Li Shuo. Investigation on Resonance Self-Shielding Calculation for PWR Cladding Materials Based on Equivalence Theory[J]. Nuclear Power Engineering, 2021, 42(1): 65-69. doi: 10.13832/j.jnpe.2021.01.0065 |
[8] | Zhao Wenbin, Yang Wenhua, Nie Liangbing, Si Junping, Xu Bin, Sun Sheng, Tong Mingyan. Development of Device for Measuring the Heat Generation Rate of Materials in Research Reactor[J]. Nuclear Power Engineering, 2021, 42(4): 45-50. doi: 10.13832/j.jnpe.2021.04.0045 |
[9] | Zhou Bing, Wang Xiaoyu, Wang Yanling, Hu bo. Safety Analysis of China Fusion Engineering Test Reactor Helium Cooled Blanket[J]. Nuclear Power Engineering, 2021, 42(S2): 29-32. doi: 10.13832/j.jnpe.2021.S2.0029 |
[10] | Liao Zhihai, Long Shaojun, Wang Peng, An Shenping, Luo Fengyan, Qiao Hongbo. Determination of Trace Uranium in Nuclear Grade Sponge Zirconium by Inductively Coupled Plasma Mass Spectrometry[J]. Nuclear Power Engineering, 2019, 40(3): 57-60. doi: 10.13832/j.jnpe.2019.03.0057 |
[11] | 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 |
[12] | Sun Kai, Feng Mingquan, Li Guoyun, Wu Yazhen, Li Furong. Assessment of Irradiation Embrittlement of Domestic RPV Material[J]. Nuclear Power Engineering, 2017, 38(S1): 125-128. doi: 10.13832/j.jnpe.2017.S1.0125 |
[13] | Ni Dongyang, Li Mancang, Wu Wenbin, Sun Wei. Neutron Penalty and Advantage Analysis of Candidate Accident-Tolerant Cladding Materials in PWRs[J]. Nuclear Power Engineering, 2015, 36(S2): 14-16. doi: 10.13832/j.jnpe.2015.S2.0014 |
[14] | Mo Huajun, Liu Xiaosong, Li Guoyun, Pan Longxuan. Research on Irradiation Effects of Domestic RPV Materials[J]. Nuclear Power Engineering, 2015, 36(S1): 198-200. doi: 10.13832/j.jnpe.2015.S1.0198 |
[15] | Yu Zhangcheng, Jie Heng. Feasibility Study on Application of Passive Safety System in Fusion-Fission Hybrid Energy Reactor[J]. Nuclear Power Engineering, 2015, 36(3): 129-134. doi: 10.13832/j.jnpe.2015.03.0129 |
[16] | XU Wenbing, Lyu Yonghong, CHEN Mingzhou, HUANG Wenyou, LI Qing. Experimental Study on Simulated Radioactive Wastes Vitrification with Arc Plasma[J]. Nuclear Power Engineering, 2015, 36(6): 175-179. doi: 10.13832/j.jnpe.2015.06.0175 |
[17] | Zu Tiejun, Wu Hongchun, Zheng Youqi, Cao Liangzhi. Burnup Calculations and Fuel Cycle Economics Analysis of Fusion-Fission Hybrid Reactor[J]. Nuclear Power Engineering, 2014, 35(S2): 34-37. doi: 10.13832/j.jnpe.2014.S2.0034 |
[18] | DANG Ying, WEN Yao-ceng, QIU Shao-yu, CHEN Yong, LUO Qiang, LI Chuan-qian. Study on Performance of Novel Overlaying Welding Materials on the Sealing Face of RPV[J]. Nuclear Power Engineering, 2013, 34(5): 84-88. |
[19] | ZU Tie-jun, WU Hong-chun, ZHENG You-qi, CAO Liang-zhi. Neutronics Analysis Code System for Hybrid Reactor[J]. Nuclear Power Engineering, 2013, 34(5): 12-15,36. |
[20] | ZHU Zheng-qing. Research and Development of Modern Large-Scale Reactor Pressure Vessel Materials[J]. Nuclear Power Engineering, 2011, 32(S2): 1-4,8. |