[1] Shengcheng Zhou, Hongchun Wu, Youqi ZhengFlexibility of ADS for minor actinides transmutation in different two-stage PWR-ADS fuel cycle scenarios[J]. Annals of Nuclear Energy,2018,111:271-279

[2] Shengcheng Zhou, Won Sik Yang, Tongkyu Park, Hongchun WuFuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations[J]. Annals of Nuclear Energy,2018,114:369-383

[3] Shengcheng Zhou, Hongchun Wu, Liangzhi Cao, Youqi ZhengUnstructured coarse mesh finite difference method to accelerate k-eigenvalue and fixed source neutron transport calculations[J]. Annals of Nuclear Energy,2018,120:367-377

[4] Shengcheng Zhou, Renzong Chen, Yiqiong Shao, Liangzhi Cao, Bofeng Bai, Hongchun WuConceptual core design study of an innovative small transportable lead‐bismuth cooled fast reactor (SPARK) for remote power supply[J]. International Journal of Energy Research,2018,42:3672-3687

[5] Youqi Zheng,Xianan Du,Zhitao Xu,Shencheng Zhou,Yong Liu,Chenghui Wan,Longfei XuSARAX: A new code for fast reactor analysis part I: Methods[J]. Nuclear Engineering and Design,2018,0:421-430

[6] Youqi Zheng,Liang Qiao,Zi'an Zhai,Xianan Du,ZhitaoXuSARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification[J]. Nuclear Engineering and Design,2018,0:41-53

[7] Tiejun Zu, Jikui Li, Wen Yin, LiangzhiCaoAccurate resonance calculation method coupling simplified embedded self-shielding method and ultra-fine group method[J]. Annals of Nuclear Energy,2018,120:198-206

[8] Jikui Li, LiangzhiCao, Tiejun Zu, HongChun WuResonance self-shielding treatment and analysis of resonance integral tables for Fully Ceramic Micro-encapsulated fuels with the Embedded Self-Shielding Method[J]. Annals of Nuclear Energy,2018,112:450-463

[9] Fan Xia, Tiejun Zu, and Hongchun WuEffect and treatment of angular dependency of multi-group total cross section and anisotropic scattering in fine-mesh transport calculation[J]. Annals of Nuclear Energy,2018,114:110-121

[10] Qingming He, Liangzhi Cao, Hongchun Wu, Benoit Forget, Kord SmithPredicting spatially dependent reaction rate for problem with nonuniform temperature distribution by subgroup method[J]. Annals of Nuclear Energy,2018,111:188-203

[11] Zhouyu Liu, Qingming He, Tiejun Zu, Liangzhi Cao, Hongchun Wu, Qian ZhangThe pseudo-resonant-nuclide subgroup method based global–local self-shielding calculation scheme[J]. Journal of Nuclear Science and Technology,2018,55:217-228

[12] Zhouyu Liu, Qingming He, Xingjian Wen, Tiejun Zu, Liangzhi Cao, Hongchun WuImprovement and optimization of the pseudo-resonant-nuclide subgroup method in NECP-X[J]. Progress in Nuclear Energy,2018,103:60-73

[13] Jun Chen, Zhouyu Liu, Chen Zhao, Qingming He, Tiejun Zu, Liangzhi Cao, Hongchun WuA new high-fidelity neutronics code NECP-X[J]. Annals of Nuclear Energy,2018,116:417-428

[14] Zhouyu Liu, Jun Chen, Liangzhi Cao, Chen Zhao, Qingming He, Hongchu WuDevelopment and verification of the high-fidelity neutronics and thermal hydraulic coupling code system NECP-X/SUBSC[J]. Progress in Nuclear Energy,2018,103:114-125

[15] Bo Wang, Zhouyu Liu, Jun Chen, Chen Zhao, Liangzhi Cao, Hongchun WuA modified predictor-corrector quasi-static method in NECP-X for reactor transient analysis based on the 2D/1D transport method[J]. Progress in Nuclear Energy,2018,108:122-135

[16] Yijun Zhang, Zhouyu Liu, Liangzhi Cao, Hongchun WuNewton-Krylov method with nodal coupling coefficient to solve the coupled neutronics/thermal-hydraulics equations in PWR transient analysis[J]. ANE,2018,118:220-234

[17] Chen Zhao, Zhouyu Liu, Liang Liang, Jun Chen, Liangzhi Cao, Hongchun WuImproved leakage splitting method for the 2D/1D transport calculation[J]. Progress in Nuclear Energy,2018,105:202-210

[18] Boning Liang, Hongchun Wu, Yunzhao LiAdaptive expansion order for diffusion Variational Nodal Method[J]. Annals of Nuclear Energy,2018,117:114-130

[19] Li Y, Li Z, Wu H, Zheng YImproved Variational Nodal Method Based on Symmetry Group Theory[J]. Nuclear Science and Engineering,2018,190:134-155