[1] | 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 |
[2] | Li Xiaoning, Ren Xueming, Zhou Bing, Chen Haiyan, Zhang Kai. Improvement of AMS Calibration Equipment in Radiation Protection Area[J]. Nuclear Power Engineering, 2017, 38(4): 47-50. doi: 10.13832/j.jnpe.2017.04.0047 |
[3] | Sun Sheng, Yang Wenhua, Tong Mingyan, Huang Gang. Development and Application of the Irradiation Facility in HFETR[J]. Nuclear Power Engineering, 2016, 37(3): 99-102. doi: 10.13832/j.jnpe.2016.03.0099 |
[4] | Ding Tongwei, Dong Bo, Zhang Qiang, Wang Linbo, Huang Jing. Discussion on Safety Regulation Major Concerns of Sodium-Cooled Fast Breeder Reactor[J]. Nuclear Power Engineering, 2016, 37(S1): 127-130. doi: 10.13832/j.jnpe.2016.S1.0127 |
[5] | Kuang Liuwei, Jiang Linzhi, Ren Liang, Yu Feiyang, Guo Chengming. Measurement Technology for Fission Gas of Irradiated HWR Fuel Elements[J]. Nuclear Power Engineering, 2016, 37(6): 86-89. doi: 10.13832/j.jnpe.2016.06.0086 |
[6] | Gao Jianbo, Li Meijuan, Wei Guohai, Liu Xiaolong, Li Yuqing, Liu Yuntao, Chen Dongfeng. A Shielding Assembly for Residual Stress Measurement of Radioactive Monitoring Sample by Neutron Diffraction[J]. Nuclear Power Engineering, 2016, 37(3): 185-188. doi: 10.13832/j.jnpe.2016.03.0185 |
[7] | ZANG Jinguang, YAN Xiao, HUANG Shanfang, CENG Xiaokang, HUANG Yanping. Investigation of Effect of Supercritical Water Properties in Pseudocritical Region on Heat Transfer Characteristics[J]. Nuclear Power Engineering, 2015, 36(1): 157-160. doi: 10.13832/j.jnpe.2015.01.0157 |
[8] | 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 |
[9] | Bai Yun, Yang Bo, Gong Jian, PenG Xianjue. Research of Neutron Time Characteristics of Subcritical Device[J]. Nuclear Power Engineering, 2014, 35(S2): 16-18. doi: 10.13832/j.jnpe.2014.S2.0016 |
[10] | YU Tao, LIU Zi-jing, XIE Jin-sen. Primary Design and Calculation of a Breeder Supercritical Water Cooled Fast Reactor[J]. Nuclear Power Engineering, 2013, 34(1): 19-25. |
[11] | 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. |
[12] | WU Yang, DOU Hai-feng, TANG Bin, HUO He-yong. Conception Design of Shielding Collimator System for High Energy Neutron Radiography with Minitype Neutron Source[J]. Nuclear Power Engineering, 2013, 34(4): 149-152. |
[13] | KONG Jing-song, GUO Wei-qun. Feasible Research on VLLW Disposal in Control Area of Nuclear Installation[J]. Nuclear Power Engineering, 2013, 34(3): 172-174. |
[14] | SAN Dong-yong, YU Tao, XIE Jin-sen, PENG Hong-hua, ZENG Zheng-kui. Study on Breeding of Fast Zone Assembly in SCWR-M[J]. Nuclear Power Engineering, 2013, 34(3): 1-4. |
[15] | LIU Zijing, YU Tao, XIE Jinsen. Primary Study on Breeding Property of Improved Supercritical Water Cooled Fast Reactor[J]. Nuclear Power Engineering, 2012, 33(6): 139-143. |
[16] | 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. |
[17] | 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. |
[18] | LI Meng, BAI Zhongxiong, XIANG Weiling, LU Yi, JIANG Zhiguo, YE Cenming, ZHANG Yi, RONG Ru. Development of Digital Instrument and Control System on Fast Neutron Critical Assembly[J]. Nuclear Power Engineering, 2012, 33(5): 100-106. |
[19] | YANG Xin, YU Ganglin, WANG Kan. Measurement of Dynamic Parameter of Sub-Critical Facility with Rossi-α Method[J]. Nuclear Power Engineering, 2011, 32(5): 9-12. |
[20] | LIU Qingjie, WU Hongchun, CAO Liangzhi. Solution of Multiplying Binary Stochastic Neutron Transport Equation in One Dimensional Spherical Geometry[J]. Nuclear Power Engineering, 2011, 32(2): 6-11. |