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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是301-310 订阅
排序:
Improved Lbe Corrosion Resistance and Mechanical Properties of Reactive Gas Pulse Sputtered Alcrfemoti/(Alcrfemoti)N Composite Multilayered High-Entropy Alloy Coatings
SSRN
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SSRN 2022年
作者: Yang, Jian Lv, Liangliang Zhou, Mingyang Chen, Qingsong Liu, Hao Zhong, Yilong Deng, Jiuguo Zhang, Wei Zhu, Changda Liu, Ning Yang, Jijun Key Laboratory of Radiation Physics and Technology of Ministry of Education Institute of Nuclear Science and Technology Sichuan University Chengdu610064 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The (HEA/HEAN)-n multilayer coatings consisting of alternating (AlCrFeMoTi)N (top) and AlCrFeMoTi layers were specially designed and successfully deposited on F/M steel substrate by reactive magnetron sputtering techn... 详细信息
来源: 评论
Characterization of High-Performance Nanostructured Wick for Heat Pipes
SSRN
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SSRN 2023年
作者: Sun, Qishi Han, Ruiyu Guo, Kailun Wang, Chenglong Zhang, Jing He, Xiaoqiang Qiu, Suizheng Su, Guanghui Tian, Wenxi Department of Nuclear Science and Technology State Key Lab. of Multiphase Flow in Power Engineering Shaanxi Key Lab. of Advanced Nuclear Energy and Technology Xi’an Jiaotong University Xi’an710049 China Key Lab. of Nuclear Reactor System Design Technology China Nuclear Power Research and Design Institute Chengdu610213 China
To investigate the best performance wick forms to support the design and fabrication of high-performance heat pipes, in this paper, two kinds of nanostructured wick were prepared by the oxidation-reduction method. The... 详细信息
来源: 评论
A Method for Hazard Analysis of Floating Nuclear Power Plant Subjected to Ship Collision
SSRN
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SSRN 2022年
作者: Xiao, Jinxiong Peng, Changhong Zhang, Hang School of Nuclear Science and Technology University of Science and Technology of China No.96 Jinzhai Road Baohe District Hefei230026 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China
Recently, a technology called floating nuclear power plant (FNPP) has been developed around the world to maximize the use of ocean and nuclear energy. The FNPP is required to investigate the impact of a ship collision... 详细信息
来源: 评论
Influence of Si Addition on the Microstructure, Mechanical and Lbe Corrosion Properties of an Amorphous Alcrfemoti High-Entropy Alloy Coating
SSRN
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SSRN 2022年
作者: Yang, Jian Zhou, Mingyang Liu, Ning Yang, Jijun Key Laboratory of Radiation Physics and Technology of Ministry of Education Institute of Nuclear Science and Technology Sichuan University Chengdu610064 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The effect of the Si addition content ranging from 3.3 to 9.1 at.% on the microstructure, mechanical properties and LBE corrosion behaviour of AlCrFeMoTi HEA coatings was investigated. The AlCrFeMoTiSix coatings still... 详细信息
来源: 评论
An interpretable machine learning-based model of turbulent Prandtl number for supercritical CO2 under buoyancy
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Applied Thermal Engineering 2025年 274卷
作者: Zhang, Ruizeng Yang, Zhengwei Liu, Yu Qiu, Qinggang Zhu, Xiaojing Key Laboratory of Ocean Energy Utilization and Energy Conservation of Ministry of Education Dalian University of Technology Dalian116024 China 703 Research Institute China State Shipbuilding Corporation Harbin150010 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Existing studies identify the failure of turbulent heat flux modeling—particularly the constant turbulent Prandtl number (Prt) assumption—as the primary cause of inaccurate heat transfer deterioration (HTD) predicti... 详细信息
来源: 评论
Study on the liquid seal discharge process in an over-pressurized accident
Study on the liquid seal discharge process in an over-pressu...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Wu, Dan Deng, Jian Du, Sijia Qian, Libo Nuclear Power Institute of China Chengdu Sichuan China Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China
In an over pressure accident, one or more pressurizer safety(or relief) valves will open due to the rapid pressure rise process. Once the safety(or relief) valves are open, the liquid seal will be discharged, and this... 详细信息
来源: 评论
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
Thermal-Mechanical Influence Aspects and Evaluation of Helical Cruciform Single Rod in Fluoride-Salt-Cooled High-Temperature Advanced reactor
SSRN
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SSRN 2024年
作者: Chen, Yiwen Zhang, Dalin Jiang, Dianqiang Li, Wei Wu, Xiaoli Tian, Wenxi Qiu, Suizheng Su, Guanghui Lu, Qi State Key Laboratory of Multiphase Flow in Power Engineering Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology School of Nuclear Science and Technology Xi’an Jiaotong University Xi’an710049 China State Key Laboratory for Strength and Vibration of Mechanical Structures Xi’an Jiaotong University Xi’an710049 China Science Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China China
Helical cruciform fuels are novel in nuclear reactors, potential to increase reactor’s power density. However, the geometry is complicated so influence of it on the fuel performance is not identified yet. In this pap... 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
The Instability Marsh Phenomenon and Marginal Stability Boundary Distortion of Density Wave Oscillation in Parallel Channels
SSRN
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SSRN 2024年
作者: Sun, Ducheng Ma, Zaiyong Lu, Q. Liu, C.W. Pan, L.M. School of Energy and Power Engineering Shandong University No. 17923 Jingshi Road Jinan250061 China Key Laboratory of Low-grade Energy Utilization Technologies and Systems Ministry of Education Chongqing400044 China Department of Nuclear Engineering and Technology Chongqing University Chongqing400044 China Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China
Density wave oscillation (DWO) in parallel channels is an important problem that has been widely studied. The marginal stability boundary (MSB) is often found to be "L " shaped on the N pch -N sub plane, but... 详细信息
来源: 评论