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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是321-330 订阅
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Simulation Method for Multiscale Failure of Optocoupler Based on Aging of Solder Layer in Photovoltaic MOSFET  2
Simulation Method for Multiscale Failure of Optocoupler Base...
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2nd IEEE International Power Electronics and Application Symposium, PEAS 2023
作者: Chen, Xuan Yao, Ran Li, Hui Lai, Wei Min, Yuan Yang, Cheng Duan, Zeyu Chen, Siyu Xing, Zhen Chongqing University State Key Laboratory of Power Transmission Equipment Technology Chongqing China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
This paper presents a simulation method for investigating the failure of optocoupler equipment (OCEP) in multi-physical fields. The method is based on the aging of the solder layer of the photosensitive field-effect t... 详细信息
来源: 评论
Electrolytic Failure Modeling of Aluminum Electrolytic Capacitor by Finite Element Method  2
Electrolytic Failure Modeling of Aluminum Electrolytic Capac...
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2nd IEEE International Power Electronics and Application Symposium, PEAS 2023
作者: Chen, Xinrui Yao, Ran Li, Hui Lai, Wei Min, Yuan Yang, Cheng Duan, Zeyu Chen, Siyu Chongqing University State Key Laboratory of Power Transmission Equipment Technology Chongqing China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
The failure rate of aluminum electrolytic capacitor (AEC) is high in power electronic systems. Due to the complex structure of AEC, it is difficult to establish an actual model, so experiments are the common way to an... 详细信息
来源: 评论
Numerical Simulation of Flow Boiling Heat Transfer in Helical Tubes Under Marine Conditions  23rd
Numerical Simulation of Flow Boiling Heat Transfer in Helica...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Yuan, Leqi Cheng, Kun Bian, Haozhi Liao, Yaping Jiang, Chenxi Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Heilongjiang Harbin China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
Lead-based cooled reactors in most countries and some small reactors at sea use helical tube steam generators. Compared with U-tubes, the convection heat transfer coefficient in the spiral tube is higher, the structur... 详细信息
来源: 评论
Demo Abstract: Observability-driven sensor deployment in smart academic environments  14
Demo Abstract: Observability-driven sensor deployment in sma...
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14th ACM Conference on Embedded Networked Sensor systems, SenSys 2016
作者: Agarwal, A. Jaiswal, K. Gudhaka, U. Munigala, V. Ramamritham, Krithi Karmakar, Gopinath Department of Computer Science Engineering Indian Institute of Technology Bombay United States Reactor Control System Design Section Bhabha Atomic Research Centre India
Saving energy without causing discomfort and without de-manding human intervention is the need of the day. It is important to develop sensor systems which not only satisfy user requirements, but also take energy consu... 详细信息
来源: 评论
A Novel Model for Dynamic Process Study of reactor Control Rod Drive Mechanism  26
A Novel Model for Dynamic Process Study of Reactor Control R...
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26th International Conference on Electrical Machines and systems, ICEMS 2023
作者: Yang, Yun Xu, Qiwei Zhang, Xuefeng Yu, Tianda Chen, Xinan Zhao, Yizhou Chongqing University National Key Laboratory of Power Transmission Equipment Technology Chongqing China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
The magnetic jack type control rod drive mechanism (CRDM) is a critical electromagnetic actuator utilized in reactors, with its movable components subject to the combined effects of electromagnetic force, liquid resis... 详细信息
来源: 评论
Performance comparison of different approximation schemes in matrix MOC
Performance comparison of different approximation schemes in...
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2018 International Conference on Physics of reactors: reactor Physics Paving the Way Towards More Efficient systems, PHYSOR 2018
作者: Yong, Zheng Peng, Minjun Zhou, Yueshan Qiang, Shenglong Ping, An Wei, Lu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Harbin150001 China
The method of characteristics (MOC) with matrix form has theoretically more favorable features than its standard application, since the time-consuming track sweeping operations are replaced with explicit solution of m... 详细信息
来源: 评论
Experimental Study on Aerosol Removal Effected by Spray Characterization  23rd
Experimental Study on Aerosol Removal Effected by Spray Char...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Hu, Peizheng Xu, Zhen Wang, Junlong Tong, Lili Cao, Xuewu School of Mechanical Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
The containment spray system is widely used in pressurized water reactor nuclear power plants, which can not only remove the heat in the containment but also remove the fission products suspended in the containment to... 详细信息
来源: 评论
Evaluation methods of fatigue in nuclear power design
Evaluation methods of fatigue in nuclear power design
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2019 Transactions of the American Nuclear Society, ANS 2019
作者: Wang, Donghui Zeng, Qingna Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 328# 1st section Chuangshun Dadao Avenue Chengdu610213 China
来源: 评论
A computer code for thermal-hydraulic analysis of steam generator with axial preheater/economizer
A computer code for thermal-hydraulic analysis of steam gene...
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AISTech 2018 Iron and Steel technology Conference and Exposition
作者: Wu, Ge He, Gening Wang, Haisong Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory NO.328 First Sec. of Changshun Ave. Shuangliu District Chengdu China
来源: 评论
The application of Lagrangian particle Tracking method in the study of steam generator sludge collector
The application of Lagrangian particle Tracking method in th...
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2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
作者: Wu, Ge Cheng, Xiang Huang, Wei Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory NO.328 First Sec. of Changshun Ave. Shuangliu District Chengdu China
During the operation of the Pressurized Water reactor recirculation steam generator, sludge particles from the feed water system and secondary system, mainly corrosion products, converge in the secondary side of steam... 详细信息
来源: 评论