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Development of neutron diffusion and transport algorithms based on finite volume method by LI Wei, LIU Xiaojing, CHAI Xiang, ZHAO Pengcheng

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Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics by JI Xu, CHAI Xiang, ZHANG Lefu, LIU Xiaojing

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Rapid Prediction of Multi-physics Coupling in Heat Pipe ReactorBased on Neural Network by ZHANG Junda, LIU Xiaojing, XIONG Jinbiao, CHAI Xiang, ZHANG Tengfei