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检索条件"机构=Science and Technology on Reactor system Design Technology Laboratory"
1292 条 记 录,以下是631-640 订阅
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Study on Acoustic-Induced Vibration (AIV) by reactor coolant pump at secondary support structure  48
Study on Acoustic-Induced Vibration (AIV) by reactor coolant...
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48th International Congress and Exhibition on Noise Control Engineering, INTER-NOISE 2019 MADRID
作者: Huang, Xuan Cai, Fengchun Wu, Wanjun Qi, Huanhuan Feng, Zhipeng Liu, Shuai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The reactor coolant pump is the core equipment of nuclear power stations. During the operation of reactor coolant pump, acoustic pulsations are generated due to nonuniform flow within the reactor coolant pump and pass... 详细信息
来源: 评论
Subway rail transit monitoring by built-in sensor platform of smartphone
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Frontiers of Information technology & Electronic Engineering 2020年 第8期21卷 1226-1238页
作者: Jian-li CONG Ming-yuan GAO Yuan WANG Rong CHEN Ping WANG School of Civil Engineering Southwest Jiaotong UniversityChengdu 610031China Key Laboratory of High-speed Railway Engineering Ministry of EducationChengdu 610031China College of Engineering and Technology Southwest UniversityChongqing 400716China National&Local Joint Engineering Laboratory of Intelligent Transmission and Control Technology Chongqing 400716China School of System Design and Intelligent Manufacturing Southern University of Science and TechnologyShenzhen 518055China
Smartphone,as a smart device with multiple built-in sensors,can be used for collecting information(e.g.,vibration and location).In this paper,we propose an approach for using the smartphone as a sensing platform to ob... 详细信息
来源: 评论
Numerical Investigation on Condensation-Induced Water Hammer in an Equal-Height-Difference Passive Heat Removal system Under Rolling Conditions
SSRN
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SSRN 2022年
作者: Wang, Zhiwei Duan, Zhongdi He, Yanping Huang, Chao Yuan, Yuchao Liu, Shiwen Li, Mingzhi State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai200240 China School of Naval Architecture Ocean & Civil Engineering Shanghai Jiao Tong University Shanghai200240 China Institute of Marine Equipment Shanghai Jiao Tong University Shanghai200240 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The investigation of condensation-induced water hammer (CIWH) under ocean conditions is crucial to the system safety of the offshore floating nuclear plants (OFNPs). This paper establishes a CIWH numerical model under... 详细信息
来源: 评论
Research on periodic test scheme of safety digital control system for nuclear power plant  27
Research on periodic test scheme of safety digital control s...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Xie, Weibo Wu, Zhiqiang Zeng, Shan Li, Yutong Hu, Qingren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The main trend in the development of the local power plant control system is to adopt digital safety DCS system with rather strong ability of self-diagnosis. Apart from the self-diagnosis, it is also necessary to carr... 详细信息
来源: 评论
Numerical methods research and fracture failure analysis for critical crack size  27
Numerical methods research and fracture failure analysis for...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Shi, Kaikai Yuan, Yanli Chen, Jianguo Bai, Xiaoming Zheng, Liangang Lu, Xifeng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
Safety analysis of fracture mechanics is an important part of structural integrity assessment and critical crack size is one ofmain concerns for fracture failure. From the perspective of mathematics, the calculation o... 详细信息
来源: 评论
The defect analysis technology study of reactor pressure vessel main bolt  27
The defect analysis technology study of reactor pressure ves...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Zheng, Liangang Zhang, Rui Huang, Qian Bai, Xiaoming Yuan, Feng Lu, Xifeng Yuan, Yanli Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The existence of non conformances and defects are inescapable during the manufacture and in service of reactor pressure vessel (RPV). After being analyzed, most of the defects have no influence on the capability and s... 详细信息
来源: 评论
Analysis of PWR SBO scenarios under refueling condition using MAAP5
Analysis of PWR SBO scenarios under refueling condition usin...
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2019 Transactions of the American Nuclear Society, ANS 2019
作者: Yuan, Peng Wu, Xiaoli Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
来源: 评论
An automatic optimization method for nuclear piping layout and mechanical analysis  27
An automatic optimization method for nuclear piping layout a...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Bai, Xiaoming Lu, Xifeng Zhang, Rui Shi, Kaikai Zheng, Liangang Huang, Qian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The piping system in the nuclear power plant is extremely complex. The traditional trial method for the optimization is time-consuming and experience-dependent. Moreover, it rarely obtains the layout with best mechani... 详细信息
来源: 评论
Acoustic performance of fluid-filled pipe with periodic helmholtz resonator considering lateral wall elasticity
Acoustic performance of fluid-filled pipe with periodic helm...
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2019 Transactions of the American Nuclear Society, ANS 2019
作者: Zeng, Qingna Wang, Donghui Zang, Fenggang Zhang, Yixiong Science and Technology on Reactor system Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
来源: 评论
Improvement and optimization of naspic SVDU engineering design in nuclear power plant according to NUREG0700  27
Improvement and optimization of naspic SVDU engineering desi...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Li, Yutong Xie, Weibo Ma, Quan Zhang, Yu Zhao, Yang Hu, Qingren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
Safety Video Display Unit (SVDU) provides the interface between operator and reactor protection system (RPS).SVDU not only displays the signals and parameters which related to safety function but also support the oper... 详细信息
来源: 评论