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检索条件"机构=Science and Technology on Reactor System Design Technology Laboratory"
1282 条 记 录,以下是161-170 订阅
排序:
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
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
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
Effect of Corrosion Damage on Structural Failure Models Under Different Boundry Conditions  23rd
Effect of Corrosion Damage on Structural Failure Models Unde...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Qian, Sheng Sun, Yu Huangfu, Yuzhao Zhang, Ke Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
Nuclear energy is an important means to deal with the energy crisis and global climate change, and the long-term safe operation of nuclear power plants strongly depends on the service behavior of structural materials.... 详细信息
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
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
Prospects for Next Generation Nuclear Power system  23rd
Prospects for Next Generation Nuclear Power System
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Zhang, Yaoxiang Yu, Hongxing Xia, Bangyang Li, Wenjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
systematically research has been carried out on the demand of economic development for low-carbon clean energy and the opportunities faced by the development of nuclear power. A new generation of nuclear power technic... 详细信息
来源: 评论
Elastic and plastic analysis of O-ring seal for reactor pressure vessel  13th
Elastic and plastic analysis of O-ring seal for reactor pres...
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13th Asia-Pacific Symposium on Engineering Plasticity and its Applications, AEPA 2016
作者: Shao, Xuejiao Zheng, Liangang Zhang, Liping Fu, Xiaolong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
The elasto-plastic analysis for reactor Pressure Vessel seal is necessary because of nuclear safety is actively demanded. The existed work based on simplified way to simulate the seal ring, such as uniform stress, spr... 详细信息
来源: 评论
Application Verification of Wireless Sensor Network in Nuclear Power Plant  1
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6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021
作者: Deng, Zhi-Guang Wu, Qian Xiang, Mei-Qiong Dong, Chen-Long Qin, Yue Li, Zhuo-Yue Sun, Yong-Sheng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The application of wireless sensor network in nuclear power plant can greatly reduce the workload of nuclear power plant cable wiring, and help to improve the automation and information level of nuclear power plant. H... 详细信息
来源: 评论