Improved PCA method for sensor fault detection and isolation in a nuclear power plant von Li, Wei, Peng, Minjun, Wang, Qingzhong

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The natural circulation flow characteristic of the core in floating nuclear power plant in rolling motion von Li, Ren, Peng, Minjun, Xia, Genglei, Sun, Lin

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Thermal-hydraulic and load following performance analysis of a heat pipe cooled reactor von Jiao, Guanghui, Xia, Genglei, Wang, Jianjun, Peng, Minjun

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Fault Diagnosis Using Bond Graphs in an Expert System von Zhou, Zhuoran, Ma, Zhanguo, Jiang, Yingying, Peng, Minjun

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Analysis of load-following characteristics for an integrated pressurized water reactor von Genglei, Xia, Minjun, Peng, Xue, Du

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Remaining Useful Life Prediction Based on Improved Temporal Convolutional Network for Nuclear Power Plant Valves von Wang, Hang, Peng, Minjun, Xu, Renyi, Ayodeji, Abiodun, Xia, Hong

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Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario von Yu, Hao, Peng, Minjun

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Simulation study on thermal characteristics of primary coolant system of lead-bismuth cooled reactor von Lu, Shuaijie, Peng, Minjun, Xia, Genglei, Zhang, Qianping

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Performance analysis of S-CO2 recompression Brayton cycle based on turbomachinery detailed design von Zhang, Yuandong, Peng, Minjun, Xia, Genglei, Wang, Ge, Zhou, Cheng

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The simulation study on natural circulation operating characteristics of FNPP in inclined condition von Li, Ren, Xia, Genglei, Peng, Minjun, Sun, Lin

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Research of two-phase flow instability in parallel narrow multi-channel system von Xia, Genglei, Peng, Minjun, Guo, Yun

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Development and Validation of Multiscale Coupled Thermal-Hydraulic Code Combining RELAP5 and Fluent Code von Sun, Lin, Peng, Minjun, Xia, Genglei, Wang, Xuesong, Wu, Mingyu

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Uncertainty Analysis on k-ε Turbulence Model in the Prediction of Subcooled Boiling in Vertical Pipes von Zhang, Xiang, Xia, Genglei, Cong, Tenglong, Peng, Minjun, Wang, Zhenhong

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Numerical Study on Coolant Flow Distribution at the Core Inlet for an Integral Pressurized Water Reactor von Sun, Lin, Peng, Minjun, Xia, Genglei, Lv, Xing, Li, Ren

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Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor von Khan, Salah Ud-Din, Peng, Minjun, Khan, Shahab Ud-Din

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Condition Monitoring of Sensors in a NPP Using Optimized PCA von Jiang, Nan, Cheng, Shouyu, Liu, Yongkuo, Peng, Minjun, Li, Wei, Wang, Hang

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Strategy Evaluation for Cavity Flooding during an ESBO Initiated Severe Accident von Cong, Tenglong, Wei, Wei, Peng, Minjun, Jiang, Nan

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Numerical investigation on local heat transfer characteristics of S-CO2 in horizontal semicircular microtube von Zhang, Yuandong, Peng, Minjun, Xia, Genglei, Cong, Tenglong

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Numerical investigation on boiling crisis in a full-length 5 × 5 fuel assembly under typical pressurized water reactor conditions von Zhang, Xiang, Xia, Genglei, Cong, Tenglong, Peng, Minjun

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An improved-MPGA and its application in OTSG load reduction characteristics optimization von Xu, Yifan, Peng, Minjun, Xia, Genglei

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