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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是551-560 订阅
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Abstract
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应用力学学报 2015年 第1期32卷 I0001-I0016页
作者: Feng Zhipeng Zang Fenggang Zhang Yixiong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 610213 Chengdu China
来源: 评论
Development and verification of SNTA code system for SCWR core steady state analysis  23
Development and verification of SNTA code system for SCWR co...
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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Wang, Lianjie Zhao, Wenbo Yang, Ping Ma, Yongqiang Lu, Di Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
A coupled neutronics/thermal-hydraulics three dimensional code system SNTA is developed for SCWR core steady state analysis by modular coupling the improved neutronics nodal methodological code and SCWR thermal-hydrau... 详细信息
来源: 评论
Simulation of esprit of hualong secondary passive residual heat removal system by using relap5  16
Simulation of esprit of hualong secondary passive residual h...
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16th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2015
作者: Feng, Li Science and Technology on Reactor System Design Technology Laboratory ChangShun Avenue 328 ShuangLiuCounty ChengDu China
A 3rd generation reactor called HuaLong is developed by China National Nuclear Corporation (CNNC). S econdary passive system (PRS) is designed to remove the residual heat during 72 hours after the reactor trips. To ve... 详细信息
来源: 评论
The instrumentation and control system for small modular reactor ACP100  9
The instrumentation and control system for small modular rea...
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9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015
作者: Chen, Zhi Song, Dan-Rong Liao, Long-Tao You, Kai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
The small modular reactor (SMR), which is coded ACP100 and developed by China National Nuclear Corporation(CNNC), is an innovative PWR based on existing PWR technology, adapting "passive" safety system and &... 详细信息
来源: 评论
Numerical simulation of sealing behavior of C-ring for reactor Pressure Vessel  23
Numerical simulation of sealing behavior of C-ring for React...
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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Dong, Yuanyuan Luo, Ying Zhang, Liping Nuclear Power Institute of China Science and Technology Reactor System Design Technology Laboratory Chengdu Sichuan China
C-ring, whose sealing behavior is the key to the sealing structure, is one of the main seal-rings for reactor Pressure Vessel. A finite element model with less simplification has been established using ANSYS APDL to s... 详细信息
来源: 评论
Study on hydrogen flame acceleration and ddt properties at elevated temperatures and pressures  23
Study on hydrogen flame acceleration and ddt properties at e...
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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Peng, Huanhuan Yu, Hongxing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
Hydrogen security is an important problem of the severe accident analysis in NPP, and the security of hydrogen detonation is more important. The hydrogen risk mainly focused on the risk of flame acceleration (FA) and ... 详细信息
来源: 评论
Numerical research on rotating speed influence and flow state distribution of water-lubricated thrust bearing  23
Numerical research on rotating speed influence and flow stat...
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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Deng, Xiao Deng, Li-Ping Huang, Wei Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Water-lubricated thrust bearing is one of the key parts in canned motor pump, for example, the RCP in AP1000, and it functions to balance axial loads. A calculation model which can handle all flow state lubrication pe... 详细信息
来源: 评论
CFD simulation of direct contact condensation phenomenon of vapor in subcooled water tank  23
CFD simulation of direct contact condensation phenomenon of ...
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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Ji, Yu Quan, Yan Zhang, Yining Zhang, Haochun Wang, Yahui Harbin Institute of Technology Harbin Heilongjiang China Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China
The direct contact condensation (DCC) is a significant phenomenon in nuclear reactor and its balance facilities, together with other chemical engineering systems. DCC occurs when the vapor is injected into the subcool... 详细信息
来源: 评论
An Algorithm for Global Path Planning and Multi-objective Optimization Using Cell Mapping
An Algorithm for Global Path Planning and Multi-objective Op...
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第十届全国动力学与控制学术会议
作者: XUE Yang XIONG Fu-rui SUN Jian-qiao Department of Mechanics Tianjin UniversityTianjin300350China Science and Technology on Reactor System Design Technology LaboratoryNuclear Power Institute of ChinaChengdu 610041China School of EngineeringUniversity of CaliforniaMercedCA 95343USA
来源: 评论
Multi-objective Optimization of Elastic Beams For Minimum Weight and Sound Radiation
Multi-objective Optimization of Elastic Beams For Minimum We...
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第十届全国动力学与控制学术会议
作者: Meng-xin He Fu-Rui Xiong Yousef Naranjani Qian Ding Jian-Qiao Sun Department of Mechanics Tianjin University Tianjin300072China Science and Technology on Reactor System Design Technology LaboratoryNuclear Power Institute of ChinaChengdu 610041China School of EngineeringUniversity of California MercedCA 95343USA
来源: 评论