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检索条件"机构=Science and Technology on Reactor System Design Technology Laboratory"
1276 条 记 录,以下是261-270 订阅
排序:
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
来源: 评论
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
来源: 评论
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
来源: 评论
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
Formally Verified a Front-End of the Trusted Code Generator for Safety I&C Software of NPPs  5th
Formally Verified a Front-End of the Trusted Code Generator ...
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5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020
作者: Lan, Lin Ma, Quan Hou, Rong-Bin Jiang, Wei Liu, Ming-Xing Yang, Fei Li, Yong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of the China Chengdu Sichuan China Harbin Engineering University Harbin China
In nuclear power plant embedded software control area, graphical control algorithms are described by Lustre program and designed with graphical editors of engineering station. After they are translated into C programs... 详细信息
来源: 评论
Burnup performance analysis for candidate materials of the LWR accident tolerant control rod  14
Burnup performance analysis for candidate materials of the L...
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14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019
作者: Liu, Yong Li, Mancang Yu, Yingrui Xiao, Peng Wang, Xingbo Zhang, Bin Wang, Dongyong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 328# Section 1 Changshun Avenue Chengdu China
The accident tolerant fuel (ATF) is considered to be one of the most advanced concepts to improve the safety of light water reactors (LWRs). The accident tolerant control rod (ATCR) is a significant aspect in the ATF ... 详细信息
来源: 评论
Research on Cylindrical Linear Induction Motor for Drive Mechanism  14
Research on Cylindrical Linear Induction Motor for Drive Mec...
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14th International Symposium on Linear Drivers for Industry Applications, LDIA 2023
作者: Niu, Xu Yu, Tianda Zhang, Lu Li, Qingzhao Huang, Siyu Liu, Yanting Wu, Hao Tang, Yuan School of Electrical Engineering Harbin Institute of Technology 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 kind of servo mechanism for the reactor control system of the nuclear power plant. This paper presents a cylindrical linear induction motor suitable for the CRDM. First, the... 详细信息
来源: 评论
DC-Side Decoupling Method of DC-link Capacitor Reduction for Single Phase PWM Rectifier
DC-Side Decoupling Method of DC-link Capacitor Reduction for...
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2020 IEEE Sustainable Power and Energy Conference, iSPEC 2020
作者: Wang, Jinxin Renyong, Peng Dai, Kailei Zhang, Zhiqiang Zhang, Ting Zhao, Junjie Chen, Qian Zhang, Jianjian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China
The integrated charging system of Electric vehicle consists of a single-phase PWM rectifier and a Buck converter. When the single-phase PWM rectifier works with unit power factor, the dc-link voltage contains a large ... 详细信息
来源: 评论
Study on the thermal-mechanical performance of SiC composites cladding under multiple conditions
Study on the thermal-mechanical performance of SiC composite...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Yin, Chunyu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No.328 section 1 changshun avenue Chengdu China
SiC has become a candidate cladding material of Accident Tolerant Fuels (ATF) due to its excellent irradiation stability and corrosion resistance. However, because SiC is a ceramic material with low toughness, brittle... 详细信息
来源: 评论
A review and correlations for two phase flow heat transfer in helically coiled tubes  27
A review and correlations for two phase flow heat transfer i...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Ma, Haifu Xu, Tao Li, Peiying Gou, Junli Yuan, Hongsheng Chen, Wei Wu, Yirui Zhong, Mingjun Gao, Yingxian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an710049 China
Helically coiled heat exchangers have been widely applied in many power conversion systems for their advantages, such as compactness and high efficiency in heat transfer. Reliable heat transfer models are required to ... 详细信息
来源: 评论