The methods of CADIS-NEE and CADIS-DXTRAN in NECP-MCX and their applications von He, Qingming, Huang, Zhanpeng, Cao, Liangzhi, Wu, Hongchun

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The CADIS-DXTRAN method in NECP-MCX for Radiation Shielding Simulations von Huang, Zhanpeng, Cao, Liangzhi, He, Qingming, Wu, Hongchun

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Development of sensitivity calculation capability of Legendre moments of scattering angular distributions in NECP-MCX von Huang, Jinlong, Cao, Liangzhi, He, Qingming, Wu, Hongchun

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Generation and analysis of independent fission yield covariances based on GEF model code von Lu, Zerun, Zu, Tiejun, Cao, Liangzhi, Wu, Hongchun

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Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX von Wu, Hongchun, Qin, Shuai, Li, Yunzhao, Shi, Jinkang, He, Qingming, Cao, Liangzhi

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Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX von Qin, Shuai, Li, Yunzhao, He, Qingming, Cao, Liangzhi, Wang, Yongping, Wu, Yuxuan, Wu, Hongchun

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Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT von Hu, Jiaqi, Qiao, Zhaopeng, Fan, Lunhe, Tang, Yongqiang, Cao, Liangzhi, Zu, Tiejun, He, Qingming, Li, Zhifeng, Wang, Sheng

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SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities von Hashim, Muhammad, Cao, Liangzhi, Zhou, Shengcheng, Ma, Rubing, Shao, Yiqiong, Chen, Renzong

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A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR von Dai, Tao, Cao, Liangzhi, He, Qingming, Wu, Hongchun, Shen, Wei

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Count Rate Analysis of the Source-range Detector for M310 von Guo, Jiandi, Liu, Zhouyu, He, Qingming, Huang, Danbin, Lin, Ziwei, Cao, Liangzhi, Wu, Hongchun

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RESONANCE CALCULATION BASED ON THE GLOBAL-LOCAL METHOD FOR THE COMPLEX GEOMETRY PROBLEMS von Cao, Lu, Liu, Zhouyu, He, Qingming, Cao, Liangzhi

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The JFNK method for the PWR's transient simulation considering neutronics, thermal hydraulics and mechanics von He, Qingming, Zhang, Yijun, Liu, Zhouyu, Cao, Liangzhi, Wu, Hongchun

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FEATURES OF THE SOURCE TERM CALCULATION CAPABILITY OF THE NECP-X CODE von Wen, Xingjian, Liu, Zhouyu, Huang, Kai, Cao, Liangzhi

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APPLICATION OF ATHERMAL RECOMBINATION CORRECTED DPA MODEL IN NUCLEAR DATA PROCESSING CODE NECP-ATLAS von Yin, Wen, Zu, Tiejun, Cao, Liangzhi

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PROCESSING RESONANCE SELF-SHIELDING EFFECT OF GADOLINIA BASED ON IMPTOVED SUPERCELL SCHEME von Li, Jikui, Zu, Tiejun, Yin, Wen, Cao, Liangzhi

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HEXAGONAL PWR-CORE MODELING AND SIMULATION WITH APPLICATION OF NECP-BAMBOO von Zhang, Cheng, Cao, Liangzhi, Li, Yunzhao, Hua, Guowei

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UNCERTAINTY ANALYSIS TO C5G7-TD BENCHMARK BASED ON THE COST METHOD von Cao, Liangzhi, Sui, Zhuojie, Wang, Bo, Wan, Chenghui, Liu, Zhouyu

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Auto MOC—A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD von Chen, Qichang, Wu, Hongchun, Cao, Liangzhi

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A new three-dimensional method of characteristics for the neutron transport calculation von Liu, Zhouyu, Wu, Hongchun, Cao, Liangzhi, Chen, Qichang, Li, Yunzhao

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METHODS FOR CALCULATION OF SELF-SHIELDED CROSS SECTIONS OF FULLY CERAMIC MICRO-ENCAPSULATED FUEL DOUBLE HETEROGENEOUS SYSTEM von He, Qingming, Yin, Wen, Liu, Zhouyu, Zu, Tiejun, Cao, Liangzhi, Wu, Hongchun

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