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

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

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Fault Diagnosis Method for Centrifugal Pumps in Nuclear Power Plants Based on a Multi-Scale Convolutional Self-Attention Network by Chen Li, Xinkai Liu, Hang Wang, Minjun Peng

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

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

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

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

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

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

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

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