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检索条件"机构=Science and Technology On Reactor System Design Technology Laboratory"
1292 条 记 录,以下是201-210 订阅
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In-situ TEM observation of the evolution of helium bubbles in Mo during He^(+)irradiation and post-irradiation annealing
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Chinese Physics B 2021年 第8期30卷 102-112页
作者: Yi-Peng Li Guang Ran Xin-Yi Liu Xi Qiu Qing Han Wen-Jie Li Yi-Jia Guo College of Energy Xiamen UniversityXiamen 361102China Fujian Research Center for Nuclear Engineering Xiamen 361102China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China
The evolution of helium bubbles in purity Mo was investigated by in-situ transmission electron microscopy(TEM)during 30 keV He^(+)irradiation(at 673 K and 1173 K)and post-irradiation annealing(after 30 keV He^(+)irrad... 详细信息
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Particle swarm optimised fuzzy PID control method for hybrid magnetic bearings  3
Particle swarm optimised fuzzy PID control method for hybrid...
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3rd International Conference on Intelligent Mechanical and Human-Computer Interaction technology, IHCIT 2024
作者: Xiong, Feng Han, Jinchang Xu, Wenhao Li, Yan Institute of Noise & vibration Naval University of Engineering Wuhan430033 China National Key Laboratory on Ship Vibration & Noise Wuhan China Science and Technology on System Design Technology Laboratory Nuclear Power institute of China Chengdu610213 China
To enhance the control effectiveness of hybrid magnetic bearings (HMBs), this paper proposes a PSO-based fuzzy PID control algorithm. The algorithm optimizes the fuzzy controller's output parameters using the Part... 详细信息
来源: 评论
DEVELOPMENT OF QUENCH ANALYSIS PROGRAM BASED ON ARSAC  29
DEVELOPMENT OF QUENCH ANALYSIS PROGRAM BASED ON ARSAC
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Zhong, Lei Yu, Hongxing Chen, Deqi Liu, Hanzhou Deng, Jian Wu, Dan Science and Technology on Reactor System Design Technology Laboratory Sichuan Chengdu610041 China Key Laboratory of Low-grade Energy Utilization Technologies and Systems Chongqing University Ministry of Education Chongqing400044 China
ARSAC is a reactor system analysis program independently developed in China. In this paper, a quench analysis module is developed based on ARSAC program. The boiling curve suitable for quench process is established an... 详细信息
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NUMERICAL ANALYSIS ON FLOW AND HEAT TRANSFER CHARACTERISTICS OF LBE IN NARROW RECTANGULAR CHANNELS  30
NUMERICAL ANALYSIS ON FLOW AND HEAT TRANSFER CHARACTERISTICS...
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30th International Conference on Nuclear Engineering, ICONE 2023
作者: Jiang, Yanming Li, Xiaochang Tian, Ruifeng Lu, Chuan Song, Zhiguang College of Nuclear Science and Technology Harbin Engineering University Harbin China Heilongjiang Provincial Key Laboratory of Nuclear Power Plant Performance and Equipment Harbin Engineering University Harbin China College of Aerospace and Civil Engineering Harbin Engineering University Harbin China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The lead-bismuth eutectic alloy (LBE) is a candidate coolant for the generation IV liquid metal reactors, and the plate-type fuel assemblies are widely used in the small or research reactors. However, the turbulent he... 详细信息
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A Mixed-State Particle Filter for Remaining Useful Life Prediction of Lithium-Ion Batteries
SSRN
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SSRN 2024年
作者: Huang, Mengqi Du, Zhengyu Lu, Ruibo Wang, Xiaoji Peng, Changhong School of Nuclear Science and Technology University of Science and Technology of China Anhui Hefei230027 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China
Lithium-ion batteries are extensively used in medical, transportation, industrial, and other applications due to rapid charging and discharging, constant power output, and light weight. Accurately predicting their rem... 详细信息
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Application of optimus in sensitivity analysis of dynamic response of reactor coolant system  27
Application of optimus in sensitivity analysis of dynamic re...
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27th International Congress on Sound and Vibration, ICSV 2021
作者: Yanli, Yuan Xianhui, Ye WenZheng, Zhang Lijuan, Li Zhenyu, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
In this paper, the sensitivity of the dynamic response of reactor coolant system to the input parameters is investigated through OPTIMUS integrated platform, taking the stiffness of the dampers which support the steam... 详细信息
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Limit load estimation for finite plates with semi-elliptical defects under tensile loading  9
Limit load estimation for finite plates with semi-elliptical...
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9th Global Conference on Materials science and Engineering, CMSE 2020
作者: Shi, K.K. Fu, X.L. Xie, H. Shao, X.J. Tian, J. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
The ASME code allows the designer to circumvent many of the problems arising in design by elastic analysis by performing plastic or limit analysis of the component. Unlike elastic analysis, these analyses take account... 详细信息
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Influence of unstable working conditions on friction torque of angular contact ball bearings  6
Influence of unstable working conditions on friction torque ...
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2023 6th World Conference on Mechanical Engineering and Intelligent Manufacturing, WCMEIM 2023
作者: Zhang, Ruoyu Yu, Yongjian Li, Jishun Xue, Yujun School of Mechatronics Engineering Henan University of Science and Technology Henan Luoyang China Henan Key Laboratory for Machinery Design and Transmission System Henan Luoyang China Longmen Laboratory Henan Luoyang China
The influence of rolling element material on friction torque of angular contact ball bearing under variable speed, variable load, and variable load conditions are studied. Based on the unstable working conditions of v... 详细信息
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Comparisons of Subgrid-Scale Models for OpenFoam Large- Eddy Simulation  7
Comparisons of Subgrid-Scale Models for OpenFoam Large- Eddy...
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2020 7th International Conference on Computer-Aided design, Manufacturing, Modeling and Simulation, CDMMS 2020
作者: Feng, Zhipeng Qi, Huanhuan Huang, Xuan Liu, Shuai Liu, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China
OpenFOAM is a free, open-source software package that can be used for the solutions of computational fluid dynamics and simulation of various fluid flow processes. Nevertheless, OpenFOAM still lacks default settings a... 详细信息
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Verification Method and Basic Guarantee of RPS Availability in Nuclear Power Plant  5th
Verification Method and Basic Guarantee of RPS Availability ...
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5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020
作者: He, Xian-Jian Liu, Ming-Ming Zhang, Qing Luo, Xiao-Jun Wen, Jing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The third generation nuclear power reactor protection system (RPS) based on computer technology, that is, safety DCS system, is designed with large-scale integrated circuits and real-time embedded software, which has ... 详细信息
来源: 评论