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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1121-1130 订阅
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The inexact gauss-newton method for core power distribution monitoring in pressurized water reactors
The inexact gauss-newton method for core power distribution ...
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2013 Winter Meeting on Transactions and Embedded Topical Meetings: Risk Management for Complex Socio-Technical systems, 2nd ANS SMR 2013 Conference, Nuclear Nonproliferation - 1st Fission to the Future
作者: Peng, Xingjie Wang, Kan Li, Qing Department of Engineering Physics Tsinghua University Beijing 100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610041 China
来源: 评论
Radial burnup profile fitting of a high burnup pellet
Radial burnup profile fitting of a high burnup pellet
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2013 ANS Annual Meeting - Next Generation Nuclear Energy: Prospects and Challenges
作者: Gao, Lijun Jiang, Shengyao Chen, Bingde Department of Engineering Physics Tsinghua University Beijing 100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610041 China
来源: 评论
Partheno-genetic algorithm approach for optimal in-core neutron detector location
Partheno-genetic algorithm approach for optimal in-core neut...
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2013 ANS Annual Meeting - Next Generation Nuclear Energy: Prospects and Challenges
作者: Peng, Xingjie Wang, Kan Li, Qing Department of Engineering Physics Tsinghua University Beijing 100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610041 China
来源: 评论
A least-squares method based on coupling coefficients for core power distribution monitoring in pressurized water reactors
A least-squares method based on coupling coefficients for co...
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2013 Winter Meeting on Transactions and Embedded Topical Meetings: Risk Management for Complex Socio-Technical systems, 2nd ANS SMR 2013 Conference, Nuclear Nonproliferation - 1st Fission to the Future
作者: Peng, Xingjie Wang, Kan Li, Qing Department of Engineering Physics Tsinghua University Beijing 100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610041 China
来源: 评论
Validation of a CFD methodology to evaluate two-phase mixing characteristics on PWR fuel rod bundle with spacer grids
Validation of a CFD methodology to evaluate two-phase mixing...
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LWR Fuel Performance Meeting, Top Fuel 2013
作者: Chen, Xi Zhang, Hong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No.25 South 2nd Ring Road Chengdu Sichuan 610041 China
As the important parts of the fuel assemblies of Pressurized Water reactors (PWR), the presence of spacer grids promotes the local heat transfer adjacent to the wall downstream the grids by causing cross and swirl flo... 详细信息
来源: 评论
The stability performances improvement through kinematic and dynamic modeling of the hopping robots
The stability performances improvement through kinematic and...
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UKACC International Conference on Control (CONTROL)
作者: Adrian Bruja Luige Vladareanu Gal Ionel Alexandru Hongbo Wang Hongnian Yu Jingjing Liu Institute of Solid Mechanics of Romanian Academy (IMSAR) Bucharest Romania School of Design Engineering and Computing Boumemouth University Poole Dorset UK Parallel Robot and Mechatronic System Laboratory of Hebei Province Key Laboratory of Advanced Forging & Stamping Technology and Science of Ministry of Education Yanshan University Qinhuangdao China
The paper presents an innovative design for a wheeled hopping robot. Our main objective was to obtain a stable and efficient robot, which can jump over obstacles and has the ability to reach a certain ledge. The innov... 详细信息
来源: 评论
Optimum Structural Material Option of reactor Vessel Internals in PWR Nuclear Power Plant
Optimum Structural Material Option of Reactor Vessel Interna...
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第三届核电厂材料与安全可靠性国际研讨会 (3rd MRNPP Symposium)
作者: WANG Qing-tian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China610041Chengdu
As a key equipment,reactor Vessel Internals influence the safety of nuclear power *** is a rigid requirement to stock of reactor Vessel Internals because of the high temperature,high pressure and high dose *** the sta... 详细信息
来源: 评论
Study on optimization of shutdown and critical model for VVER-1000
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Hedongli Gongcheng/Nuclear Power Engineering 2013年 第SUPPL.1期34卷 80-83+98页
作者: Lu, Zong-Jian Liu, Tong-Xian Wang, Jin-Yu Wu, Lei Yu, Ying-Rui National Key Laboratory of Reactor System Design Technology Nuclear Power Institute of China Chengdu 610041 China
On the premise of safety, economy is one of the important objectives of nuclear power plants. For VVER-1000, there are several cases of operation modes when the plant is off the grid, such as the critical operation af... 详细信息
来源: 评论
design of a new solution for the wheeled hopping robot
Design of a new solution for the wheeled hopping robot
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UKACC International Conference on Control (CONTROL)
作者: Jingjing Liu Hongbo Wang Hongnian Yu Lili Zhang Luige Vladareanu Adrian Bruja Gal I. Alexandru Parallel Robot and Mechatronic System Laboratory of Hebei Province Key Laboratory of Advanced Forging & Stamping Technology and Science of Ministry of Education Yanshan University Qinhuangdao China College of Electrical Engineering Yanshan University Qinhuangdao China School of Design Engineering and Computing Bournemouth University Poole UK Robotics and Mechatronic Department Institute of Solid Mechanics Bucharest Romania
In recent years many researchers are trying to combine wheeled movement with legged movement or hopping movement to strengthen the robots adaptability to environment. Hybrid robots are playing a more and more importan... 详细信息
来源: 评论
Sensitivity analyses of steam generator tube thickness on induced-sgtr in sbo accident
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2013 International Conference on Energy Research and Power Engineering, ERPE 2013
作者: Qiu, Jin-Rong Peng, Chang-Hong Guo, Yun Laboratory on Steam Power System Wuhan Second Ship Design and Research Institute Wuhan Hubei 430064 China School of Nuclear Science and Technology University of Science and Technology of China Hefei Anhui 230026 China
For nuclear power plant, station black- out (SBO) is the events that contribute significantly to the level-I core damage risk. For an SBO, it is assumed that both the off-site power and on-site diesel generators fail ... 详细信息
来源: 评论