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检索条件"机构=Science and Technology on Reactor System Design Technology"
2723 条 记 录,以下是11-20 订阅
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A NUMERICAL SIMULATION METHOD FOR THE VIBRATION REDUCTION OF MR ISOLATOR BASED ON IMPEDANCE TEST  30
A NUMERICAL SIMULATION METHOD FOR THE VIBRATION REDUCTION OF...
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30th International Congress on Sound and Vibration, ICSV 2024
作者: Wenzheng, Zhang Peng, Xiangfeng Zhihao, Yuan Guojiang, Liao Xiaozhou, Jiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
It’s important to choose suitable method to simulate the vibration reduction of the isolators. For a long time, scholars and engineers have been working hard to reduce the error between numerical simulation and exper... 详细信息
来源: 评论
NUMERICAL INVESTIGATION ON THE THERMAL-HYDRAULIC AND FIV CHARACTERISTICS IN LBE-COOLED HELICAL CRUCIFORM FUEL AND WIRE-WRAPPED FUEL  31
NUMERICAL INVESTIGATION ON THE THERMAL-HYDRAULIC AND FIV CHA...
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2024 31st International Conference on Nuclear Engineering, ICONE 2024
作者: Qi, Zhang Haoyu, Wang Cao, Junxian Yuanming, Li Chenxi, Li Zhenhai, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The lead bismuth eutectic (LBE) cooled fast reactor in one of the General 4 advanced reactors, which plays significant role in the nuclear fuel cycle. In the recent years, the wire-wrapped fuel with four wires surroun... 详细信息
来源: 评论
Surface-PMSM Sensorless Control Strategy Based on Reduced-Order Linear Kalman Filter Cooperating with Prediction Error Rolling Compensation
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IEEE Transactions on Power Electronics 2025年 第8期40卷 10804-10815页
作者: Xu, Sang Shen, Anwen Tang, Qipeng Wang, Miaomiao Luo, Pan Luo, Xin Xu, Jinbang National Key Laboratory of Science and Technology on Multispectral Information Processing Key Laboratory of Image Processing and Intelligent Control School of Artificial Intelligence and Automation Wuhan430074 China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
Kalman filter (KF) is increasingly attracted for sensorless control of surface permanent magnet synchronous motors (SPMSMs) due to its strong robustness against measurement and system noise. However, conventional meth... 详细信息
来源: 评论
STUDY ON DYNAMIC RESPONSE OF reactor CORE BARREL UNDER PUMP-INDUCED PULSATING PRESSURE  30
STUDY ON DYNAMIC RESPONSE OF REACTOR CORE BARREL UNDER PUMP-...
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30th International Congress on Sound and Vibration, ICSV 2024
作者: Ye, Xianhui Cai, Fengchun Huang, Xuan Feng, Zhipeng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The flow-induced vibration (FIV) problem is widely present in nuclear power plants and has caused numerous engineering accidents. Therefore, it has been highly valued by the nuclear engineering community for a long ti... 详细信息
来源: 评论
Research on The FPGA Reconfiguration technology Based on RS Code for Nuclear Applications  15
Research on The FPGA Reconfiguration Technology Based on RS ...
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15th IEEE Global Reliability and Prognostics and Health Management Conference, PHM-Beijing 2024
作者: Chen, Qi Wang, Fanyu He, Jinyu Zhao, Yang Wang, Heng Huang, Qichang Lei, Minjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Field Programmable Gate Array (FPGA) is now widely used in nuclear safety Instrumentation and Control (I&C) systems and operates core features like communication, signal capturing and processing, peripheral contro... 详细信息
来源: 评论
RESEARCH ON VIBRATION CHARACTERISTICS OF FLOATING RAFT ISOLATION system BASED ON STRUCTURAL PARAMETERS  30
RESEARCH ON VIBRATION CHARACTERISTICS OF FLOATING RAFT ISOLA...
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30th International Congress on Sound and Vibration, ICSV 2024
作者: Wang, Yu Lai, Jian-Yong Cai, Long-Qi Li, Zhao-Wen Liu, Jia Wang, Ran Liu, Shuai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
As an important noise source for nuclear power systems, pump equipment needs continuous operation and always in a high vibration level. With the development of vibration isolation technology, floating raft vibration i... 详细信息
来源: 评论
MATLAB/Simulink-Based Simulation Study of Small Pressurized Water reactor Nuclear Steam Supply system  4
MATLAB/Simulink-Based Simulation Study of Small Pressurized ...
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4th Asia Conference on Information Engineering, ACIE 2024
作者: Chen, Jie Xiao, Kai Mengwei, Mengwei Zhao, Zhao Huang, Ke Yang, Pengcheng Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China
Accurate and reliable modeling and simulation is the key prerequisite for intelligent control technology research of nuclear power plant. For the nuclear steam supply system (NSSS) of small pressurized water reactor u... 详细信息
来源: 评论
Key technology of a New Potential Economical Desalination Method for Small Nuclear Power  23rd
Key Technology of a New Potential Economical Desalination Me...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Li, Siguang Gan, Yiran Li, Yi Liang, Tiebo Science and Technology on Reactor System Design Technology Laboratory Sichuan Chengdu China
With the rapid development of distributed energy, small nuclear power has been widely concerned by researchers because of its inherent advantages. Keeping circulating water in a low salinity state is an important fact... 详细信息
来源: 评论
INVESTIGATION ON THE APPLICATION OF MRF DAMPER BASED ON-OFF SEMI-ACTIVE VIBRATION CONTROL ON THE reactor COOLANT PUMP  30
INVESTIGATION ON THE APPLICATION OF MRF DAMPER BASED ON-OFF ...
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30th International Congress on Sound and Vibration, ICSV 2024
作者: Liao, Guojiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
The seismic design of the reactor coolant pump is important for the nuclear power plant. In this study, the magnetorheological fluid damper (MRF damper) is introduced to the supporting structure of reactor coolant pum... 详细信息
来源: 评论
RESEARCH OF MODEL FOR LOCA NONLINEAR DYNAMIC ANALYSIS OF reactor COOLANT system  30
RESEARCH OF MODEL FOR LOCA NONLINEAR DYNAMIC ANALYSIS OF REA...
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30th International Congress on Sound and Vibration, ICSV 2024
作者: Yanli, Yuan Xianhui, Ye Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
The Loss of Coolant Accident (LOCA) is one of the most serious accidents in nuclear power plants. According to the requirements of the United States Nuclear Regulatory Commission (USNRC) SPR, the dynamic response anal... 详细信息
来源: 评论