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检索条件"机构=Science and Technology on Reactor Design Technology"
676 条 记 录,以下是521-530 订阅
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Ratcheting Behavior of SA508-3 Steel at Elevated Temperature:Experimental Observation and Simulation
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Acta Metallurgica Sinica(English Letters) 2017年 第9期30卷 822-828页
作者: Jun Tian Yu Yang Li-Ping Zhang Xue-Jiao Shao Juan Du Qian-Hua Kan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Applied Mechanics and Structure Safety Key Laboratory of Sichuan Province School of Mechanics and EngineeringSouthwest Jiaotong University
A series of monotonic uniaxial tensile tests, strain-controlled and stress-controlled cyclic tests of SA508-3 steel were conducted from 25 to 350℃. Results showed that the steel exhibited temperature-dependent cyclic... 详细信息
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Multi-objective Optimization of Non-uniform Beam for Minimum Weight and Sound Radiation
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Transactions of Tianjin University 2017年 第4期23卷 380-393页
作者: Furui Xiong Mengxin He Yousef Naranjani Qian Ding Jianqiao Sun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China School of Mechanical Engineering Tianjin University School of Engineering University of California Merced
A multi-objective optimization of non-uniform beams is presented for minimum radiated sound power and weight. The transfer matrix method is used to compute the structural and acoustic responses of a non-uniform beam a... 详细信息
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Preliminary evaluation of U 3 Si 2 -FeCrAl fuel performance in light water reactors through a multi-physics coupled way
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Nuclear Engineering and design 2018年 328卷 27-35页
作者: Yanan He Ping Chen Yingwei Wu G.H. Su Wenxi Tian Suizheng Qiu Shaanxi Engineering Research Center of Advanced Nuclear Energy School of Nuclear Science and Technology Xi’an Jiaotong University Xi’an City 710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610213 China
U 3 Si 2 -FeCrAl fuel system is a potential choice for Accident Tolerant Fuel (ATF) for its higher uranium density, improved fuel thermal conductivity and stronger oxidation resistance. In this work, a new multi-physi... 详细信息
来源: 评论
Fatigue crack growth model for edge sliding mode  14
Fatigue crack growth model for edge sliding mode
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14th International Conference on Fracture, ICF 2017
作者: Shi, K.K. Zheng, B. Bai, X.M. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The inherent law between fatigue behaviours of shear-type representative volume element and mode-II fatigue crack growth is found in the range of cycle plastic zone near the crack tip. Prediction models for mode-II fa... 详细信息
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Stress intensity factors for penetrate radial cracks in reactor coolant pump flywheel by weight function method  14
Stress intensity factors for penetrate radial cracks in reac...
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14th International Conference on Fracture, ICF 2017
作者: Shi, K.K. Zheng, B. Gao, S.Q. Chen, J.G. Lv, X. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Stress intensity factors for penetrate radial crack at center of keyway and at keyway corner under the plane stress, the plane strain and the three dimensional, based on weight function method, is determined by finite... 详细信息
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Improved core design of the supercritical water-cooled reactor CSR1000
Improved core design of the supercritical water-cooled react...
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Wang, Lianjie Lu, Di Yang, Ping Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
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Large eddy simulation of turbulent flow in rod bundle with spacer grids
Large eddy simulation of turbulent flow in rod bundle with s...
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Zonglan, Wei Xiao, Chu Yu, Zhang Songtao, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
来源: 评论
The study on overall I&C system scheme for floating nuclear power plant ACP100S and ACP25S  10
The study on overall I&C system scheme for floating nuclear ...
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10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017
作者: Chen, Zhi Long-Tao, Liao Dan-Rong, Song You, Kai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
Floating nuclear power plant (FNPP) is built on the offshore platform and it is defined as a kind of Small and Modular reactor(SMR) due to its power level. The FNPP can provide power supply, fresh water and high tempe... 详细信息
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Calculation of higher eigenpairs of the transport equation Using IRAM based on domain decomposition
Calculation of higher eigenpairs of the transport equation U...
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Wu, Wenbin Yu, Yingrui Li, Qing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
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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
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