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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是201-210 订阅
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Numerical study of fuel melting and molten migration based on the mps method
Numerical study of fuel melting and molten migration based o...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Lei, Zhong Deng, Jian Li, Wei Wu, Xiaoli Deng, Chunrui Nuclear Power Institute of China Chengdu Sichuan China Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China
Core melting and molten migration behavior are hot and difficult issues in the field of nuclear reactor severe accident research. The Moving Particle Semi-implicit (MPS) meshless method has potential to simulate free-... 详细信息
来源: 评论
The statistical analyses on the bubble contact diameters in the vertical narrow channel
The statistical analyses on the bubble contact diameters in ...
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2019 Transactions of the American Nuclear Society, ANS 2019
作者: Lu, Qi Liu, Yu Liu, Wei Chen, Xi He, Hangxing Zhou, Linglan Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China Nuclear Power Institute of China Chengdu610041 China
来源: 评论
Prediction of the critical heat flux in subcooled flow boiling in round tube using an improved mechanistic model
Prediction of the critical heat flux in subcooled flow boili...
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18th International Conference on Nuclear Engineering, ICONE18
作者: Na, Yu Yu, Zhang National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute of China Chengdu Sichuan 610041 China
Among the existing CHF models, the bubble crowding model and the liquid sublayer dryout model have been well accepted for subcooled flow boiling. But both of the two models couldn't give explanation about some det... 详细信息
来源: 评论
REVIEW OF RISK-INFORMED SAFETY design CONCEPT, METHOD AND APPLICATION  30
REVIEW OF RISK-INFORMED SAFETY DESIGN CONCEPT, METHOD AND AP...
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30th International Conference on Nuclear Engineering, ICONE 2023
作者: Gong, Lanxin Zhong, Mingjun Peng, Changhong School of Nuclear Science and Technology University of Science and Technology of China Hefei China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Since the NRC issued the PSA policy in 1995, PSA containing risk information has been widely used in supervision and design. Subsequently, the concept of "risk-informed" has gained more and more recognition,... 详细信息
来源: 评论
KYLIN-V2.0 code calculation ability verification based on VERA benchmark
KYLIN-V2.0 code calculation ability verification based on VE...
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2020 International Conference on Physics of reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
作者: Wang, Dongyong Yu, Yingrui Peng, Xingjie Wang, Chenlin Liu, Kun Chai, Xiaoming Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China Nuclear Power Institute of China Chengdu610213 China
Virtual Environmental for reactor Analysis (VERA) benchmark was released by the Consortium for Advanced Simulation of Light water reactors (CASL) project in 2012. VERA benchmark includes more than ten problems at diff... 详细信息
来源: 评论
Natural convective heat transfer from a heated slender vertical tube in a cylindrical tank  16
Natural convective heat transfer from a heated slender verti...
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16th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2015
作者: Xian, Lin Jiang, Guangming Yu, Hongxing Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China Nuclear Power Institute of China Chengdu610041 China
Natural convective heat transfer in enclosures is widely researched in extensive range of engineering application such as passive residual heat removal system (PRHRS) in nuclear plant, solar collectors and cooling of ... 详细信息
来源: 评论
Research on analysis and modeling methods for lbloca in nuclear power plants based on autonomous loca analysis platform arsac
Research on analysis and modeling methods for lbloca in nucl...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Zhou, Jiayue Wu, Dan Ding, Shuhua Jiang, Guangming Nuclear Power Institute of China Chengdu Sichuan China Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China
In order to meet the demand of continuous innovation of technologies and the general trend of autonomous nuclear power plants design and export of nuclear power plants, it is necessary to develop an autonomous LOCA an... 详细信息
来源: 评论
Preliminary study on the radiation heat removal capacity in SMR core under high temperature condition
Preliminary study on the radiation heat removal capacity in ...
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2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
作者: Li, Zhongchun Ding, Shuhua Li, Songwei Deng, Jian Nulcear Power Institute of China Chengdu610041 China Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China
The advanced fuel design, such as accident tolerant fuel (ATF) was design concept to withstand the high temperatures for extreme condition. When it was equipped in reactor core, the heat removal by radiation would be ... 详细信息
来源: 评论
Large eddy simulation of turbulent flow in the rod bundle with different spacer grids  23
Large eddy simulation of turbulent flow in the rod bundle wi...
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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
作者: Wei, Zonglan Yu, Zhang Liu, Songtao Science and Technology on Reactor System Design Technology Laboratory NPIC Chengdu Sichuan China Nuclear Power Design and Research Sub-Institute NPIC Chengdu Sichuan China
Large eddy simulation(LES) of the swirling flow in the rod bundle subchannels with spacer grids are presented. According to the rod bundle flow benchmark experiment, the 5×5 rod bundle with a split-type spacer gr... 详细信息
来源: 评论
Microstructure and impact toughness of 16MND5 reactor pressure vessel steel manufactured by electrical additive manufacturing
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Journal of Iron and Steel Research International 2020年 第8期27卷 992-1004页
作者: Xi-kou He Chang-sheng Xie Li-jun Xiao Ying Luo Di Lu Zheng-dong Liu Xi-tao Wang Institute for Special Steels China Iron and Steel Research InstituteBeijing 100081China Collaborative Innovation Center of Steel Technology University of Science and Technology BeijingBeijing 100083China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610041SichuanChina Southern Additive Science and Technology Co. Ltd.Foshan 528225GuangdongChina
Electrical additive manufacturing can improve manufacturing efficiency and reduce the cost of 16MND5 reactor pres-sure vessel steel. Impact tests were conducted to compare the impact toughness of 16MND5 steels manufac... 详细信息
来源: 评论