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检索条件"机构=Science and Technology on Reactor System Design Technology"
2733 条 记 录,以下是51-60 订阅
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Effect of He/dpa ratio on bubble characteristics in Fe9Cr1.5W0.4Si F/M steel during irradiation and annealing
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Journal of Materials science & technology 2024年 第30期197卷 17-24页
作者: Dewang Cui Kefei Pei Ziqi Cao Yipeng Li Yifan Ding Yuanming Li Shichao Liu Guang Ran College of Energy Xiamen UniversityXiamen361102China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213China College of Chemistry and Chemical Engineering Xiamen UniversityXiamen361005China Fujian Provincial Nuclear Energy Engineering Technology Research Center Xiamen361102China Nuclear Power Institute of China Chengdu610213China
The He production rate(i.e.,He/dpa)in nuclear reactors strongly affects the degradation of material *** is an important but not yet fully understood ***,the effect of He/dpa on bubble char-acteristics in Fe9Cr1.5W0.4S... 详细信息
来源: 评论
Study on Multi-Motor Synchronization Control for Nuclear Island Main Equipment Transporter Based on Improved Virtual Line-Shafting Structure  11th
Study on Multi-Motor Synchronization Control for Nuclear Isl...
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11th Frontier Academic Forum of Electrical Engineering, FAFEE 2024
作者: Sheng, Beining Song, Beibei An, Yanbo Du, Hua Cui, Shumei School of Electrical Engineering and Automation Harbin Institute of Technology Harbin150001 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The existing drive method of the main equipment transporter of the nuclear island makes the transporter have frequent jamming problems when the transporter going straight and turning, which affects the safety during t... 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
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FEASIBILITY AND SAFETY ANALYSIS OF SOLID-STATE reactor FOR LUNAR SURFACE EXPLORATION  31
FEASIBILITY AND SAFETY ANALYSIS OF SOLID-STATE REACTOR FOR L...
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2024 31st International Conference on Nuclear Engineering, ICONE 2024
作者: Yugao, Ma Jiahao, Lu Yue, Liu Suyi, Zhang Muhao, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China College of Nuclear Technology and Automation Engineering Chengdu University of Technology Chengdu610059 China
The Fission Surface Power system is a feasible solution for future lunar surface exploration energy supply, with the solid-state reactor being considered a primary candidate. This paper presents a modeling and analysi... 详细信息
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Investigation on influence of gamma irradiation on piezoelectric and resonance characteristics of surface acoustic wave resonators  5
Investigation on influence of gamma irradiation on piezoelec...
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5th International Conference on Mechanical Engineering and Materials, ICMEM 2024
作者: Sun, Lei Peng, Bin Yang, Yuntao Sun, Zhaofeng Zhu, Jialiang Zhang, Wanli State Key Laboratory of Electronic Thin Films and Integrated Devices University of Electronic Science and Technology of China Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In this work, an evaluation towards influence of high-dose gamma irradiation on surface acoustic wave (SAW) resonators, is reported. The single-port SAW resonators are fabricated using Lithium niobate (LiNbO3) and Cat... 详细信息
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Fault Severity Classification based on Information Flow and Support Vector Machines  8
Fault Severity Classification based on Information Flow and ...
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8th International Conference on Energy system, Electricity, and Power, ESEP 2023
作者: Yang, Xiaohua Liu, Zhikun Fang, Weiyang Huang, Tao Liu, Jie Yang, Jinghua Ren, Changan Department of Compute Science University of South China Hengyang421001 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China
Fault severity describes the level of impact caused by a fault. In the event of a malfunction in a nuclear power plant, a vast amount of data and alarms are generated, making it challenging for operators to identify a... 详细信息
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A Transformer-based Time Series Prediction Model with Contrastive Learning for Nuclear Power system State Monitoring  15
A Transformer-based Time Series Prediction Model with Contra...
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15th IEEE Global Reliability and Prognostics and Health Management Conference, PHM-Beijing 2024
作者: Gou, Pengfei Zheng, Daiwei Tang, Lei Liu, Mengjuan School of Information and Software Engineering University of Electronic Science and Technology of China UESTC Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China NPIC Chengdu China
Prognostics and Health Management (PHM) is currently the mainstream solution for the condition monitoring and maintenance of industrial systems. In PHM, the system condition is monitored by monitoring the operational ... 详细信息
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Analysis of contribution degree of vibration transmission of bolted structure  29
Analysis of contribution degree of vibration transmission of...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Liu, Shuai Li, Wanyou Huang, Xuan Xiong, Furui Jiang, Xiaozhou Deng, Dliwei Harbin Engineering University Harbin China Science and Technology on Reactor System Design Technology Laboratory Chengdu China Technology on Reactor System Design Technology Laboratory Chengdu China
In practical engineering, the vibration transmission between bolted structures supported by cantilever beams involves many factors, including the friction between plates and the bolt connection relationship. The vibra... 详细信息
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Investigation on crack propagation of SiCf/SiC composite via PF-CZM method
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International Journal of Advanced Nuclear reactor design and technology 2024年 第1期6卷 9-13页
作者: Qiu, Bowen Li, Zhuang Liang, Shuang Zhang, Cheng Wei, Chong Xiao, Zhong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China School of Mechanical Civil Engineering and Architecture Northwestern Polytechnical University Xi'an710072 China Science and Technology on Thermo Structural Composite Materials Laboratory Northwestern Polytechnical University Xi'an710072 China
SiCf/SiC composite materials had become a research hotspot in the fields of aerospace materials and nuclear materials in recent years. This materials have high strength, radiation resistance, high temperature resistan... 详细信息
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THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONICS with COMSOL and RMC  29
THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONIC...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Liu, Zhenhai Qi, Feipeng Zhou, Yi Li, Quan Chen, Ping Chen, Hao Ma, Chao Zhao, Bo Li, Chenxi Science and Technology on Reactor System Design Technology Laboratory Npic Chengdu China
Predicting fuel behavior in the reactor is a typical multiphysics coupling problem. The traditional fuel performance analysis adopts a decoupling way. To provide a higher fidelity tool for fuel performance simulation,... 详细信息
来源: 评论