[1] Wen Yin, Tiejun Zu, Qingming He, Liangzhi CaoMulti-group effective cross section calculation method for Fully Ceramic Micro-encapsulated fuel[J]. Annals of Nuclear Energy,2019,125:26-37

[2] Tiejun Zu ⇑ , Jialong Xu, Yongqiang Tang, Huchao Bi, Fei Zhao, Liangzhi Cao, Hongchun WuNECP-Atlas: A new nuclear data processing code[J]. Annals of Nuclear Energy,2019,123:153-161

[3] Jialong Xu, Tiejun Zu, Liangzhi CaoDevelopment and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas[J]. Progress in Nuclear Energy,2019,110:301-310

[4] Tiejun Zu, Fan Xia, Hongchun WuAn improved fitting method for subgroup parameters based on the heterogeneous cells[J]. Journal of Nuclear Science and Technology,2019

[5] Qingming He, Zhouyu Liu, Linagzhi Cao, Hongchun WuError analysis of approximations and treatments commonly made in multi-group library and self-shielding calculation based on NECP-X[J]. Annals of Nuclear Energy,2019,130:418-430

[6] Zhuojie Sui, Liangzhi Cao ， Chenghui Wan  , Xiaoyang ZouCovariance-Oriented Sample Transformation: A New Sampling Method for Reactor-Physics Uncertainty Analysis[J]. Annals of Nuclear Energy,2019,134:452-463

[7] Yongping Wang*, Yunzhao Li, Tengfei Zhang, et al.Generalized Partitioned Matrix Acceleration for Variational Nodal Diffusion Method[J]. Nuclear Science and Engineering,2019,193:652-662

[8] Yongping Wang*, Tengfei Zhang, E. E. Lewis, et al.Three-dimensional variational nodal method parallelization for pin resolved neutron transport calculations[J]. Progress in Nuclear Energy,2019,117:0-0

[9] Linfang Wei, Youqi Zheng, Hongchun WuImprovement of few-group cross-section generation in fast reactor analysis system SARAX[J]. Annals of Nuclear Energy,2019,132:149-160

[10] Zhuojie Sui, Liangzhi Cao, Chenghui Wan, Xiaoyang ZouCovariance-oriented-sample-transformation--A-new-sampling[J]. Annals of Nuclear Energy,2019,134:542-463

[11] Chenghui Wan, Zhuojie Sui, Bo Wang, Liangzhi Cao, Zhouyu Liu, Jason HouNuclear-data-uncertainty-propagation-in-transient-simula[J]. Annals of Nuclear Energy,2019

[12] Youqi Zheng, Liang Qiao, Chenghui Wan, Liangzhi Cao, Yong LiuSensitivity-analysis-and-similarity-evaluation-of-sodium[J]. Annals of Nuclear Energy,2019,125:283-290

[13] Chenghui Wan, Liangzhi Cao, Hongchun WuUncertainty-quantification-for-the-first-cycle-modeling-a[J]. Annals of Nuclear Energy,2019,133:378-386

[14] Liang Qiao, Youqi Zheng , Chenghui WanUncertainty-quantification-of-sodium-cooled-fast-reactor-ba[J]. Annals of Nuclear Energy,2019,128:433-442

[15] Chenghui Wan, Liang Qiao, Youqi Zheng, Liangzhi Cao, Hongchun WuValidation-of-SARAX-for-the-China-Fast-Reactor-with-the[J]. Annals of Nuclear Energy,2019,127:188-195

[16] Yunzhao Li, Boning Liang, Hongchun Wu, Zhipeng Li, Jiewei YangHeterogeneous discontinuity factor treatment in Variational Nodal Method[J]. Annals of Nuclear Energy,2019,127:341-350

[17] Tiejun Zu, Fan Xia, Hongchun WuAn improved fitting method for subgroup parameters based on the heterogeneous cells[J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY,2019,56:179-192

[18] Shengcheng Zhou, Liangzhi Cao, Hongchun Wu, Bofeng Bai, Chi Lei, Yifan Zhang2019_SPARK-LS - A novel design of a compact liquid chloride salt cooled fast reactor based on tube-in-duct fuel concept[J]. Annals of Nuclear Energy,2019,128:248-255

[19] Qi Zheng, Wei Shen, Yunzhao Li, Hongchun Wu, Liangzhi CaoA deterministic-stochastic energy-hybrid method for neutron-transport calculation[J]. Annals of Nuclear Energy,2019,128:292-299

[20] ZhouyuLiu, Chen Zhao, Lu Cao, Hongchun Wu, Liangzhi CaoThe material-region-based 2D/1D transport method[J]. Annals of Nuclear Energy,2019,128:1-11