Large-scale Dynamics of Line-driven Winds with the Re-radiation Effect von Zhu, Yi, Xie, Jinsen

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Fault Diagnosis of Nuclear Power Plant Based on Sparrow Search Algorithm Optimized CNN-LSTM Neural Network von Zhang, Chunyuan, Chen, Pengyu, Jiang, Fangling, Xie, Jinsen, Yu, Tao

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Development and Validation of a Nuclear Power Plant Fault Diagnosis System Based on Deep Learning von Liu, Bing, Lei, Jichong, Xie, Jinsen, Zhou, Jianliang

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A fast sampling algorithm for energy-angle distributions of bremsstrahlung photon for radiotherapy applications von Wasaye, Muhammad Abdul, Yu, Tao, Xie, Jinsen, Chen, Zhenping, Ni, Zining

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Research on Data-Driven Methods for Solving High-Dimensional Neutron Transport Equations von Peng, Zhiqiang, Lei, Jichong, Ni, Zining, Yu, Tao, Xie, Jinsen, Hong, Jun, Hu, Hong

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Research on the Measurement Method of the Prompt Neutron Decay Constant Based on LHS-DMD-Rossi-Alpha von Li, Junguang, Xie, Jinsen, Deng, Nianbiao, Zhang, Erpin, Wu, Zhiqiang, Tong, Ji, Yu, Tao

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The Influence Mechanism of Neutron Kinetics of the Accelerator-Driven Subcritical Reactor Based on the Fast/Thermal Neutron Spectra by Monte Carlo Homogenization Method von Deng, Nianbiao, Xie, Chao, Hou, Cheng, Li, Zhulun, Xie, Jinsen, Yu, Tao

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Quantitative Analysis Study of Effects of Nuclide Concentration Uncertainties on Biases and Bias Uncertainties in Criticality Calculation Method von Ni, Zining, Chen, Xirong, Xie, Jinsen, Wasaye, Muhammad Abdul, Yu, Tao

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Performance of different absorber materials and move-in/out strategies for the control rod in small rod-controlled pressurized water reactor: A study based on KLT-40 model von Wu, Zhiqiang, Xie, Jinsen, Chen, Pengyu, Xiao, Yingjie, Ni, Zining, Liu, Tao, Deng, Nianbiao, Sun, Aikou, Yu, Tao

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Effect of KLT-40S Fuel Assembly Design on Burnup Characteristics von Zhou, Zedong, Xie, Jinsen, Deng, Nianbiao, Chen, Pengyu, Wu, Zhiqiang, Yu, Tao

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Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor von Zhao, Pengcheng, Liu, Zijing, Yu, Tao, Xie, Jinsen, Chen, Zhenping, Shen, Chong

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Design and implementation of cloud platform for nuclear accident simulation von Chen, Pengyu, Chen, Xirong, Xie, Jinsen, Xiong, Wenbin, Yu, Tao

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Selection of burnable poison in plate fuel assembly for small modular marine reactors von Xu, Shikun, Yu, Tao, Xie, Jinsen, Li, Zhulun, Xia, Yi, Yao, Lei

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Burnable Poison Selection and Neutronics Analysis of Plate Fuel Assemblies von Xu, Shikun, Yu, Tao, Xie, Jinsen, Yao, Lei, Li, Zhulun

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Dynamic Characteristics of Accelerator-Driven Subcritical Reactor With Self-Adapting Multi-Mode Core Few-Group Constants von Deng, Nianbiao, Xie, Jinsen, Hou, Cheng, Zeng, Wenjie, Chen, Zhenping, Yu, Tao, Zhao, Pengcheng, Liu, Zijing, Xie, Chao, Xie, Qin

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Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor von Deng, Nianbiao, Yu, Tao, Xie, Jinsen, Chen, Zhenping, Xie, Qin, Zhao, Pengcheng, Liu, Zijing, Zeng, Wenjie

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Corrigendum: Validation of Doppler Temperature Coefficients and Assembly Power Distribution for the Lattice Code KYLIN V2.0 von Jichong, Lei, Jinsen, Xie, Zhenping, Chen, Tao, Yu, Chao, Yang, Bin, Zhang, Chen, Zhao, Xiangyang, Li, Jiebo, Wu, Nianbiao, Deng

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Validation of Doppler Temperature Coefficients and Assembly Power Distribution for the Lattice Code KYLIN V2.0 von Jichong, Lei, Jinsen, Xie, Zhenping, Chen, Tao, Yu, Chao, Yang, Bin, Zhang, Chen, Zhao, Xiangyang, Li, Jiebo, Wu, Huajian, Zhang, Nianbiao, Deng

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RBF-based event-triggered fixed-time stable and chattering-free controller for load following of the pressurized water reactor von Liu, Hongliang, Zeng, Wenjie, Xie, Jinsen, Luo, Run

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A fuzzy-PID composite controller for core power control of liquid molten salt reactor von Zeng, Wenjie, Jiang, Qingfeng, Xie, Jinsen, Yu, Tao

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