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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是111-120 订阅
排序:
Research and design on the Control Rod Drive Mechanism Power Supply and Control Strategy for the Nuclear Power Plants Based on Silicon-Controlled Rectifier
Research and Design on the Control Rod Drive Mechanism Power...
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International Conference on Power Electronics and Motion Control (IPEMC)
作者: A. Mingzhou Xu B. Gao Zheng C. Zerun Zhao D. Ping Yang E. Yusheng Peng Science and Technology on Reactor System Design Technology Laboratory China Southwest Jiaotong University China
Due to the characteristics of large output current ripple and long current rise and fall times in the current rod control power supply basedsilicon-controlled rectifier, a decoupling nonlinear adaptive control is *** ... 详细信息
来源: 评论
Improving the ductility of laser directed energy deposited borated stainless steel by increasing laser power
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Journal of Manufacturing Processes 2025年 145卷 494-507页
作者: Huang, Sheng Li, Qingyu Zhang, Xiaoyu Cui, Bin Li, Dichen Zhang, Anfeng Miao, Kai State Key Laboratory for Manufacturing Systems Engineering School of Mechanical Engineering Xi'an Jiaotong University Xi'an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Mechanical and Electrical Engineering Yuncheng University Yuncheng044000 China Co. Ltd. Chengdu610091 China
Borated stainless steels (BSSs) are extensively applied in the nuclear energy industry due to boron's excellent thermal neutron absorption capacity, but large and brittle borides formed during casting result in a ... 详细信息
来源: 评论
Direct Contact Condensation Characteristics of Steam Injection into Cold-Water Pipe Under Rolling Condition  23rd
Direct Contact Condensation Characteristics of Steam Injecti...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Wang, Zhiwei He, Yanping Duan, Zhongdi Huang, Chao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Direct contact condensation (DCC) is widely occurred in nuclear power systems and leads to undesired phenomena such as condensation-induced water hammer. For ocean nuclear power ships, DCC is inevitable in the passive... 详细信息
来源: 评论
Effects of Inlet Conditions on the Two-Phase Flow Water Hammer Transients in Elastic Tube  23rd
Effects of Inlet Conditions on the Two-Phase Flow Water Hamm...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Zhao, Zixiang Duan, Zhongdi Xue, Hongxiang Yuan, Yuchao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Two-phase flow water hammer events occur in the pipelines of the nuclear power systems and lead to transient and violent pressure shock to tube structures. For the sake of operation safety, the occurrence and severity... 详细信息
来源: 评论
MATLAB/Simulink-Based Simulation Study of Small Pressurized Water reactor Nuclear Steam Supply system
MATLAB/Simulink-Based Simulation Study of Small Pressurized ...
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Information Engineering (ACIE), IEEE Asia Conference on
作者: Jie Chen Kai Xiao Mengwei Mengwei Zhao Zhao Ke Huang Pengcheng Yang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Accurate and reliable modeling and simulation is the key prerequisite for intelligent control technology research of nuclear power plant. For the nuclear steam supply system (NSSS) of small pressurized water reactor u...
来源: 评论
Research and Verification of the One-Step Resonance and Transport Methods Based on the Openmoc Code
SSRN
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SSRN 2024年
作者: Zhao, Chen Wang, Lianjie Chen, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
With the continuous improvement of computer hardware capabilities, the one-step method in reactor physics has become one of the important research directions in recent two decades. OpenMOC is an open-source MOC code d... 详细信息
来源: 评论
Research on Hybrid Modeling Method Based on Mechanism Model and BP Neural Network
Research on Hybrid Modeling Method Based on Mechanism Model ...
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Information Engineering (ACIE), IEEE Asia Conference on
作者: Jie Chen Yanqiu Zheng Qing Chu Guanfu Jiang Jing Li Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
reactor system modeling is the premise of reactor control system design. The common commercial thermal and hydraulic analysis programs like RELAP5, RETRAN have complex structure and slow operational speed, which are n...
来源: 评论
Reliability Analysis of Nuclear Safety-Class DCS ESFAS Based on FTA  7th
Reliability Analysis of Nuclear Safety-Class DCS ESFAS Based...
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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023
作者: Zhang, Xu Peng, Hao Feng, Shi-Man Yang, Jing-Hua Chen, Shi-Yong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China PowerChina Sichuan Electric Power Engineering Co. Ltd Chengdu610041 China
Nuclear safety-class DCS realizes reactor safety protection function, which is directly related to the safe and stable operation of nuclear power plants, so its reliability should be analyzed and optimized. In this pa... 详细信息
来源: 评论
NUMERICAL INVESTIGATION ON DIRECT CONTACT CONDENSATION CHARACTERISTICS OF STEAM INJECTION INTO COLD-WATER PIPE UNDER HEAVING CONDITION  30
NUMERICAL INVESTIGATION ON DIRECT CONTACT CONDENSATION CHARA...
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30th International Conference on Nuclear Engineering, ICONE 2023
作者: Wang, Zhiwei He, Yanping Duan, Zhongdi Huang, Chao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai200240 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Direct contact condensation (DCC) is widely appeared in the nuclear power plants and will lead to serious temperature and pressure fluctuations. For ocean nuclear power plants, the DCC is inevitably affected by the se... 详细信息
来源: 评论
Modelling Analysis of Non-uniform Flow and Heat Transfer in Parallel Rectangular Channels During Flow Blockage Condition  23rd
Modelling Analysis of Non-uniform Flow and Heat Transfer in ...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Chen, Jiayue Chen, Huandong Wang, Xiaoyu Wang, Zefeng Sino-French Institute of Nuclear Engineering and Technology Sun Yat-Sen University Zhuhai610213 China Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
In order to establish the non-uniform flow and heat transfer modelling method in parallel rectangular channels, as an additional technique and tool for safety analysis of plate-type fuel, one dimensional two-fluid mod... 详细信息
来源: 评论