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检索条件"机构=Science and Technology on Reactor System Design Technology"
2774 条 记 录,以下是41-50 订阅
排序:
Research and Application of Endogenous Security Active Defense technology for Domestic Nuclear Safety-Level Gateway Equipment  7th
Research and Application of Endogenous Security Active Defen...
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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023
作者: Li, Yong Liu, Ming-Xing Peng, Hao Hou, Rong-Bin Ma, Quan Wang, Ru-Qiao Liang, Gen-Hua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Gateway is a protective equipment at the boundary of the nuclear safety-level I&C system. Aiming at the unknown threat across the boundary of information physical space, this paper studies several key technologies... 详细信息
来源: 评论
SMR FEEDWATER system ANALYSIS  30
SMR FEEDWATER SYSTEM ANALYSIS
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30th International Conference on Nuclear Engineering, ICONE 2023
作者: Zhu, Ye Liang, Qiao Xianwei, Liao Zhiyun, Cai Minghao, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
The once through steam generator has great heat transfer capacity and compact structure. Some small module reactors (SMR) applied once through steam generatorfor its high thermal efficiency. The thermal hydraulic char... 详细信息
来源: 评论
Response Time Analysis Method of Safety-Level DCS in Nuclear Power Plant Based on Probability Theory  1
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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023
作者: Wen, Jing He, Xian-Jian Chen, Zhao Wan, Zi-Yuan Wu, Zhi-Qiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610000 China
Aiming at the incompleteness and inadequacy of the response time analysis method of the current nuclear power plant safety-level digital-control system (DCS), this paper proposes an analysis method based on probabilit... 详细信息
来源: 评论
Openfoam Simulation of Damping Controlled Fluidelastic Instability  23rd
Openfoam Simulation of Damping Controlled Fluidelastic Insta...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Feng, Zhipeng Liu, Shuai Qi, Huanhuan Huang, Xuan Lv, Xi Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
A parallel triangular tube bundle with a single flexible tube is taken as the object, and the most dangerous mechanism of flow induced vibration in the tube bundle structure, fluidelastic instability (FEI) is studied ... 详细信息
来源: 评论
Analytical Method Research of Source Term for Steam Generator Tube Rupture Accident of Small Modular reactor  23rd
Analytical Method Research of Source Term for Steam Generato...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Xia, Ming-ming Wang, Jun-long Zhu, Jian-ping Tian, Chao Liu, Jia-jia Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sicuan Chengdu China
Based on the full reference to the existing engineering practice and safety review experience, and considering the actual design characteristics of the small modular reactor ACP100, a set of source term analysis metho... 详细信息
来源: 评论
An Unsupervised Learning-Based Framework for Effective Representation Extraction of reactor Accidents  23rd
An Unsupervised Learning-Based Framework for Effective Repre...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Li, Chengyuan Li, Meifu Qiu, Zhifang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
Compared to knowledge-based diagnostic systems, data-based methods tend to perform better in terms of speed and accuracy in diagnosing reactor accidents, and have significant advantages in terms of scalability of mode... 详细信息
来源: 评论
Research on Thermal-Hydraulic Model and Characteristics of Lead Cooled Traveling Wave reactor  23rd
Research on Thermal-Hydraulic Model and Characteristics of L...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Zhang, Yaoxiang Zhang, Xue Yu, Hongxing Du, Sijia Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Traveling wave reactor (TWR) is an advanced nuclear power system, which can keep the total amount of fissionable nuclides constant during its lifetime through the transformation of fissionable nuclides in the reactor,... 详细信息
来源: 评论
Influence of Impedance Characteristics of Perforated Plate on Pump-Induced Pulsation in reactor  23rd
Influence of Impedance Characteristics of Perforated Plate o...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Yu, Sun Fengchun, Cai Sheng, Qian Yuzhao, Huangfu Ke, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
In primary circuit, pump-induced pulsation (PIP) of coolant may cause fatigue failure of reactor components. In this article, a three-dimensional numerical model of PIP was established by COMSOL, theory of acoustic im... 详细信息
来源: 评论
Development of a Method for Detecting Cutting Points of Wilted Leaves Using 2D Image Keypoints and 3D Point Cloud
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Journal of Institute of Control, Robotics and systems 2024年 第11期30卷 1237-1244页
作者: Kang, Byeong Chang Jung, Ho Won Kim, Jong Hyeong Department of Mechanical Design and Robot Engineering Seoul National University of Science and Technology Korea Republic of Department of Mechanical System and Design Engineering Seoul National University of Science and Technology Korea Republic of
In agriculture, removing withered leaves is crucial for maintaining crop quality and preventing pests and diseases. This paper proposes a method for estimating the pose of wilted leaves and removing wilted leaves. Whi... 详细信息
来源: 评论
Semi-empirical and semi-quantitative lightweight shielding design method
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Nuclear science and Techniques 2023年 第3期34卷 109-124页
作者: Song-Chuan Zheng Qing-Quan Pan Huan-Wen Lv Song-Qian Tang Xiao-Jing Liu College of Smart Energy Shanghai Jiao Tong UniversityShanghai 200240China School of Nuclear Science and Engineering Shanghai Jiao Tong UniversityShanghai 200240China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610200China
The lightweight shielding design of small reactors is a popular research *** on a small helium-xenon-cooled solid reactor,the effects of neutron and photon shielding sequence and the number of shielding layers on the ... 详细信息
来源: 评论