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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261-270 订阅
排序:
Uncertainty Quantification of Spray Nozzle Fatigue Analysis Under Transient Load  1
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作者: Liu, Zhenyu Li, Lijuan Zhang, Liping Li, Hui Shao, Xuejiao Jiang, Lu Zhang, Ying Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China No. 328 Changshun Avenue Chengdu Sichuan610200 China
In this paper, the randomness concept of input parameters is introduced into the design of nuclear equipment, and the uncertainty analysis of input parameters is carried out for fatigue analysis. Taking the pressurize... 详细信息
来源: 评论
Study on analysis method of loca dynamic response for steam generator heat transfer tube  29
Study on analysis method of loca dynamic response for steam ...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Lu, Xifeng Xiong, Furui Wang, Xinjun Ai, Honglei Li, Bingjin Shao, Xuejiao Yang, Kang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China
The equivalent effect relationship formula of LOCA hydraulic load in the bend section of the heat transfer tube of the steam generator is deduced. The hydraulic load factors affecting the stress of the heat transfer t... 详细信息
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Preliminary experimental validation of multi-loop natural circulation model based on RELAP5/SCDAPSIM/MOD 4.0
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International Journal of Advanced Nuclear reactor design and technology 2020年 2卷 25-33页
作者: Zahraddeen, Abbati Chen, Jiarui Cheng, Kun Zhao, Fulong Tan, Sichao Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Harbin 150001 China Abuja Nigeria Science and Technology on Reactor Design Technology Nuclear Power Institute of China Chengdu610213 China
Passive safety systems mostly working on the principles of natural circulation are given much priority in increasing the reliability of reactors’ inherent safety features. In view of this, many researchers carry out ... 详细信息
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Peridynamic Simulation for Thermal and Mechanical Behavior of Manufactured Structures with MIG Welding  1
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作者: Li, Hui Zhang, Liping Liu, Zhenyu Li, Lijuan Zhang, Yixiong Shao, Xuejiao Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China No. 328 Changshun Avenue Chengdu Sichuan610200 China
A new numerical simulation method is developed for the evaluation of thermal and mechanical analyses of manufactured structures with Metal Inert Gas (MIG) welding on the basis of the peridynamics. The peridynamic form... 详细信息
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Experimental Study of Turbulent Bubbly Flow in 180-Degree Elbow by PIV-PS Technique
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International Journal of Advanced Nuclear reactor design and technology 2022年 第3期4卷 109-120页
作者: Chen, Wuguang Li, Songwei Mu, Xiaocheng Yang, Fan Yan, Zhigang Sun, Jiajin Huang, Guangyuan Cai, Kangbei Hu, Yuanbiao Yin, Junlian Wang, Dezhong School of Nuclear Science and Engineering Shanghai Jiao Tong University Shanghai200240 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China CGN Inspection Technology Co. Ltd. Jiangsu Suzhou215100 China
The curvature effect and bubbles are the key factors that affect the gas-liquid two-phase flow and turbulent characteristics in the 180-degree elbow. Limited by the difficulty of experimental measurement and numerical... 详细信息
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Study on numerical model of vortex shedding for three-way pipe  48
Study on numerical model of vortex shedding for three-way pi...
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48th International Congress and Exhibition on Noise Control Engineering, INTER-NOISE 2019 MADRID
作者: Liu, Shuai Feng, ZhiPeng Wu, WanJun Jiang, XiaoZhou Huang, Xuan Qi, HuanHuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China. No. 328 Changshun Avenue Shuangliu Chengdu China
The three-way pipe vortex shedding phenomenon is the main excitation source for pipe vibration, which can lead to the generation of acoustic resonance. The existing researches mainly focus on air and wet steam, howeve... 详细信息
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A preliminary study on irradiation growth behavior modelling of N36 zirconium alloy tube
A preliminary study on irradiation growth behavior modelling...
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Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance
作者: Yifei, Miao Yongjun, Jiao Kun, Zhang Shuo, Xing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Nuclear Power Institute of China China
As a new kind of Zr-Sn-Nb series alloy, N36 has not been explored in irradiation growth behavior before. In this paper, four empirical correlations including power, logarithmic, exponential and hyperbolic tangent law ... 详细信息
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Kinematics and Dynamics Analysis of a Quadruped Walking Robot with Parallel Leg Mechanism
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Chinese Journal of Mechanical Engineering 2013年 第5期26卷 881-891页
作者: WANG Hongbo SANG Lingfeng HU Xing ZHANG Dianfan YU Hongnian Parallel Robot and Mechatronic System Laboratory of Hebei Province Yanshan University Key Laboratory of Advanced Forging & Stamping Technology and Science of Ministry of Education Yanshan University Xi’an University of Architecture and Technology Science and Technology Research Institute Yanshan University School of Design Engineering and ComputingBournemouth University
It is desired to require a walking robot for the elderly and the disabled to have large capacity,high stiffness,stability,***,the existing walking robots cannot achieve these requirements because of the weight-payload... 详细信息
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Study on irradiation damage of rpv steels based on coupling cluster dynamics and crystal plasticity finite element method
Study on irradiation damage of rpv steels based on coupling ...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Wang, Xiaotong Luo, Ying Dong, Yuanyuan Yao, Weihua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China
Irradiation hardening is one of the most important aging effects of reactor pressure vessel (RPV) steel in long-term service. A number of studies have indicated that irradiation hardening is mainly caused by irradiati... 详细信息
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Characteristic Analysis of a Cylindrical Linear Motor for Drive Mechanism  26
Characteristic Analysis of a Cylindrical Linear Motor for Dr...
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26th International Conference on Electrical Machines and systems, ICEMS 2023
作者: Niu, Xu Yu, Tianda Zhang, Lu Zhang, He Harbin Institute of Technology School of Electrical Engineering Harbin China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
The control rod drive mechanism (CRDM) is a critical device in nuclear plants. This paper proposes a kind of CRDM applying the cylindrical linear induction motor (CLIM). First, the structure and the working principle ... 详细信息
来源: 评论