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检索条件"机构=Science and Technology on Reactor System Design Technology Lab"
730 条 记 录,以下是581-590 订阅
CFD simulation and validation of turbulent mixing in a rod bundle with vaned spacer grids based on LDV test
CFD simulation and validation of turbulent mixing in a rod b...
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2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
作者: Chen, Xi Li, Songwei Li, Zhongchun Du, Sijia Zhang, Yu Peng, Huanhuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No. 328 Section 1 Changshun Avenue Shuangliu sub-district Chengdu Sichuan610213 China
Spacer grids with mixing vanes are generally used in fuel assemblies of Pressurized Water reactor (PWR), because that mixing vanes could enhance the lateral turbulent mixing in subchannels. Thus, heat exchangements ar... 详细信息
来源: 评论
Improvement and validation of free convection heat transfer model for tube bundle in RELAP5
Improvement and validation of free convection heat transfer ...
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Lin, Xian Guangming, Jiang Fan, Yang Feng, Li Xu, Ran Science and Technology on Reactor System Design Technology Laboratory 328# Changshun Avenue Chengdu Sichuan610213 China Nuclear Power Institute of China 328# Changshun Avenue Chengdu Sichuan610213 China
来源: 评论
Study of bottom reflooding in a narrow rectangular Channel  17
Study of bottom reflooding in a narrow rectangular Channel
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17th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2017
作者: Xu, Wei Yao, Jun Liu, Xiaojing Cheng, Xu Zeng, Wei School of Nuclear Science and Engineering Shanghai Jiao Tong University 800 Dongchuan Road Minhang District Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Cheng Du610041 China
For the purpose of figuring out the thermal-hydraulic behaviors during bottom reflooding in the narrow rectangular channel of plate-type fuel reactor, experimental apparatus was established to simulate the bottom refl... 详细信息
来源: 评论
Thermo-hydraulic research for supercritical water reactor during power-raising phase of startup  25
Thermo-hydraulic research for supercritical water reactor du...
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2017 25th International Conference on Nuclear Engineering, ICONE 2017
作者: Li, Zichao Zhou, Tao Lanyu, Zhou Liu, Liang Chen, Juan Hongxing, Yu Nuclear Safety and Thermal Power Standardization Institute North China Electric Power University Changping District Beijing China School of Nuclear Science and Technology University of South China Hengyang 421001 China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
Thermal characteristics during startup of CSR1000 are directly related to the security of supercritical water reactors. The heat transfer model during power-raising phase is built according to the sliding pressure mod... 详细信息
来源: 评论
Deep learning for LiDAR point clouds in autonomous driving: A review
arXiv
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arXiv 2020年
作者: Li, Ying Ma, Lingfei Zhong, Zilong Liu, Fei Cao, Dongpu Li, Jonathan Chapman, Michael A. Department of Geography and Environmental Management University of Waterloo 200 University Avenue West WaterlooN2L 3G1 Canada School of Data and Computer Science Sun Yat-Sen University Guangzhou510006 China Xilinx Technology Beijing Limited Beijing100083 China Waterloo Cognitive Autonomous Driving Lab University of Waterloo N2L 3G1 Canada Departments of System Design Engineering University of Waterloo WaterlooONN2L 3G1 Canada Department of Civil Engineering Ryerson University TorontoONM5B 2K3 Canada
Recently, the advancement of deep learning in discriminative feature learning from 3D LiDAR data has led to rapid development in the field of autonomous driving. However, automated processing uneven, unstructured, noi... 详细信息
来源: 评论
Fracture mechanics analysis of cracked structures using weight function and neural network method
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IOP Conference Series: Materials science and Engineering 2018年 第1期372卷
作者: J G Chen F G Zang Y Yang K K Shi X L Fu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China China
Stress intensity factors(SIFs) due to thermal-mechanical load has been established by using weight function method. Two reference stress states sere used to determine the coefficients in the weight function. Results w...
来源: 评论
A core design of breeding BWR
A core design of breeding BWR
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Guo, Rui Yamaji, Akifumi Qin, Xue Ji, Wenhao Jiang, Zhumin Wang, Shuai Cai, Yun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Huayang Chengdu610041 China Cooperative Major in Nuclear Energy Graduate School of Advanced Science and Engineering Waseda University 3-4-1 Okubo Tokyo169-8555 Japan
来源: 评论
Application of Deep Learning in Fundus Image Processing for Ophthalmic Diagnosis - A Review
arXiv
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arXiv 2018年
作者: Sengupta, Sourya Singh, Amitojdeep Leopold, Henry A. Gulati, Tanmay Lakshminarayanan, Vasudevan Theoretical and Experimental Epistemology Lab School of Optometry and Vision Science University of Waterloo Ontario Canada Department of System Design Engineering University of Waterloo Ontario Canada Department of Computer Science and Engineering Manipal Institute of Technology India
An overview of the applications of deep learning in ophthalmic diagnosis using retinal fundus images is presented. We also review various retinal image datasets that can be used for deep learning purposes. Application... 详细信息
来源: 评论
The parareal method for solving space-dependent neutron kinetics equations in hexagonal-z geometry
The parareal method for solving space-dependent neutron kine...
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2017 Transactions of the American Nuclear Society, ANS 2017
作者: Cai, Yun Hou, Jingjing Peng, Xingjie Li, Qing Wang, Kan Department of Engineering Physics Tsinghua University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China China Core and Fuel Management Department CNNP Nuclear Power Operation Management Co. Ltd China
来源: 评论
CFD simulation of NUPEC PSBT subchannel test under high pressures  17
CFD simulation of NUPEC PSBT subchannel test under high pres...
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17th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2017
作者: Li, Quan Yu, Junchong Jiao, Yongjun Liu, Yanghua Gu, Mingfei Avramova, Maria Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Engineering Physics Tsinghua University Beijing100084 China Department of Nuclear Engineering North Carolina State University NC27695 United States
In this paper, Eulerian two-fluid model coupled with extended wall boiling model is used to simulate the subcooled boiling flow in PSBT subchannel test. Improved sub-models are used to describe the heat flux distribut... 详细信息
来源: 评论