A new surrogate method for the neutron kinetics calculation of nuclear reactor core transients by Xiaoqi Li, Youqi Zheng, Xianan Du, Bowen Xiao

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Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation by Xianan Du, Xuewen Wu, Youqi Zheng, Yongping Wang

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Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method by Yichen Yang, Youqi Zheng, Xianan Du, Hongchun Wu

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Verification of a two-step code system MCS/RAST-F to fast reactor core analysis by Tuan Quoc Tran, Alexey Cherezov, Xianan Du, Deokjung Lee

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The applicability study and validation of TULIP code for full energy range spectrum by Wenjie Chen, Xianan Du, Rong Wang, Youqi Zheng, Yongping Wang, Hongchun Wu

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Conceptual design of a MW heat pipe reactor by Yunqin Wu, Youqi Zheng, Qichang Chen, Jinming Li, Xianan Du, Yongping Wang, Yushan Tao

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Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis by Xianan Du, Jiwon Choe, Sooyoung Choi, Woonghee Lee, Alexey Cherezov, Jaeyong Lim, Minjae Lee, Deokjung Lee

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