Resultados da busca - Minjun Peng

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

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Improved PCA method for sensor fault detection and isolation in a nuclear power plant por 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 por Chen Li, Xinkai Liu, Hang Wang, Minjun Peng

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An intelligent fault detection method for PWR-type nuclear power plants using neuro-encoder binary cells por Furqan Arshad, Minjun Peng, Fazle Haseeb, Wasiq Ali

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

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

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

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

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

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

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

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

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Hybrid data augmentation for uncertainty mitigation in machine learning based fault diagnosis of pressurized water reactor nuclear power plants por Fazle Haseeb, Minjun Peng, Furqan Arshad, Khan Awais, Wasiq Ali

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Effects of feedback color and icon shape on touch interaction performance under unstable conditions of floating nuclear power platforms por Jing Shui, Chunhui Dong, Fuqiu Ma, Minjun Peng, Wenxiu Yang

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

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

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Path planning in radioactive environment of nuclear facilities based on modified A-star algorithm and search neighborhood optimization por Biao Zhang, Xingfu Cai, Guoqiang Li, Xiaomeng Li, Minjun Peng, Haowei Wang

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Design and performance analysis of 15MWth SCO2-cooled micro reactor por Yuandong Zhang, Ren Li, Bowen Zhang, Yiran Miao, Chao Guo, Genglei Xia, Minjun Peng

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Study on the release and migration of radioactive materials under LBLOCA in small pressurized water reactor por Miao Yang, Xingfu Cai, Minjun Peng, Yapei Zhang, Haoli Wang, Haowei Wang, Biao Zhang

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