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

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

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

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

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

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

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DEVELOPMENT OF DECAY HEAT MODEL FOR RAST-K von Dzianisau, Siarhei, Park, Jinsu, Choi, Sooyoung, Cherezov, Alexey, Du, Xianan, Lee, Deokjung

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MACROSCOPIC CROSS SECTIONS GENERATION BY MONTE CARLO CODE MCS FOR FAST REACTOR ANALYSIS von Nguyen, Tung Dong Cao, Lee, Hyunsuk, Du, Xianan, Dos, Vutheam, Tran, Tuan Quoc, Lee, Deokjung

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

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SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification von Zheng, Youqi, Qiao, Liang, Zhai, Zi'an, Du, Xianan, Xu, Zhitao

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SARAX: A new code for fast reactor analysis part I: Methods von Zheng, Youqi, Du, Xianan, Xu, Zhitao, Zhou, Shencheng, Liu, Yong, Wan, Chenghui, Xu, Longfei

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The acceleration of improved Tone's method in advanced reactor lattice neutron spectrum calculation von Du, Xianan, Yang, Yichen, Zheng, Youqi, Wang, Yongping, Wu, Hongchun

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Extension of SARAX code system for reactors with intermediate spectrum von Wei, Linfang, Zheng, Youqi, Du, Xianan, Wu, Hongchun

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Development and verification of the coupling code of discrete ordinates and Monte Carlo methods von Zhang, Yunsheng, Wang, Yongping, Du, Xianan, Zheng, Youqi

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The low-enriched uranium core design of a MW heat pipe cooled reactor von Wu, Yunqin, Zheng, Youqi, Tao, Yushan, Liu, Xiaoyue, Du, Xianan, Wang, Yongping

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Multi-parameter nuclear data adjustment for sodium fast reactor von Wang, Yongping, Qiao, Liang, Du, Xianan, Zheng, Youqi

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Development of optimal framework SARAX/DAKOTA for multiple objective optimization of fast reactor and its application von Du, Xianan, Li, Xiaoqi, Zheng, Youqi, Wang, Yongping, Zhai, Zi'an

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Investigation on radioisotopes evolution in the fuel of Lead-Bismuth eutectic (LBE) cooled SPARK-NC core von Raza, Sohail Ahmad, Hashim, Muhammad, Cao, Liangzhi, Du, Xianan, Jiang, Longwen

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Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER von Du, Xianan, Tao, Yushan, Zheng, Youqi, Wang, Chenglong, Wang, Yongping, Qiu, Suizheng, Zhang, Bin, Zhai, Zi'an

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Validation of SARAX code system using the SFR operational tests von Du, Xianan, Zheng, Youqi, Wang, Yongping, Zhai, Zi'an, Zhou, Hang

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