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检索条件"机构=Science and Technology on Reactor System Design Technology Laboratory"
1275 条 记 录,以下是101-110 订阅
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Computational fluid dynamics simulations of spray tests in a multicompartment construction with an Eulerian–Lagrangian approach
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Frontiers in Energy Research 2024年 12卷
作者: Lu, Yazhe Ran, Xu Wei, Zonglan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
This paper is an investigation of the gas mixing and depressurization effects of containment spray on hydrogen risk during a typical severe accident in a light water reactor (LWR). Two spray tests (ST3_0 and ST3_1) we... 详细信息
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Deep Learning Based Fault Diagnosis for Chemical Process with Statistical Feature Fusion  42
Deep Learning Based Fault Diagnosis for Chemical Process wit...
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42nd Chinese Control Conference, CCC 2023
作者: Zhang, Lei Xia, Hao Cha, Bao School of Control Science and Control Engineering Dalian University of Technology Dalian116024 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610091 China
The existing fault diagnosis methods based on deep neural networks mostly rely on process data for fault classification and diagnosis, which makes it difficult to distinguish minor faults with similar data features. T... 详细信息
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Dictionary-Labeled A∗: Optimal Path-and-Posture Planning for Mobile Robots with Turning Radius Constraints
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IEEE Robotics and Automation Letters 2024年 第12期9卷 10740-10747页
作者: Yang, Chen Lin, Zhiyun Southern University of Science and Technology School of System Design and Intelligent Manufacturing Shenzhen518055 China Southern University of Science and Technology Shenzhen Key Laboratory of Control Theory and Intelligent Systems Shenzhen518055 China Peng Cheng Laboratory Shenzhen518066 China
In this study, we introduce an algorithm called Dictionary-Labeled A∗ (DL-A∗), which addresses the critical problem of path-and-posture planning for mobile robots with turning radius constraints. DL-A∗ utilizes a dict... 详细信息
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Single event effect evaluation of different communication ways based on 40nm SRAM-FPGA  3
Single event effect evaluation of different communication wa...
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3rd International Conference on Artificial Intelligence and Computer Engineering, ICAICE 2022
作者: Zhao, Xu Du, Xuecheng Xiong, Xu Chen, Zhi Jiang, Wei School of Nuclear Science and Technology University of South China Hengyang City421001 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
Field-programmable gate array (FPGA) is now considered by an increasing number of designers in various fields of application, such as space and aircraft embedded control systems, image and signal processing. It is a p... 详细信息
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Study on 131I Source Term in reactor Coolant Under Shutdown Transient Condition  23rd
Study on 131I Source Term in Reactor Coolant Under Shutdown ...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Fu-ting, Jing Huan-wen, L.V. Ming-Ming, X.I.A. Zhang-Han, Y.E. Xi-long, Gao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Fuqing Nuclear Power Co. Ltd Fuqing China
131I activity in coolant under transient conditions is an important input for SGTR accident source term analysis in nuclear power plant, which directly affects whether the radioactive consequences of SGTR can meet the... 详细信息
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STARTUP ANALYSES OF A HELIUM-XENON GAS-COOLED reactor  30
STARTUP ANALYSES OF A HELIUM-XENON GAS-COOLED REACTOR
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30th International Conference on Nuclear Engineering, ICONE 2023
作者: Ma, Yugao Bao, Hui Lu, Jiahao Ding, Shuhua Zhang, Meng Yang, Xiaolong Deng, Jian Zhang, Muhao 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 Helium-Xenon (He-Xe) gas-cooled reactor uses a He-Xe gas mixture to remove the heat from the reactor core. It has the characteristics of a long life-cycle, simple operation, and high power-mass ratio, which has an... 详细信息
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design of Code Generator for Safety Level I&C Software of NPPs  6th
Design of Code Generator for Safety Level I&C Software of NP...
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6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021
作者: Wei, Jiang Lin, Lan Bin, Yang Hou, Rong-Bin Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of the China Sichuan Chengdu China
The function block diagram is used to design control algorithm of nuclear safety-level I&C (Instrumentation & Control) system. Then it is converted into C code by code generator. And the C code is downloaded i... 详细信息
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RESEARCH ON LOCA DYNAMIC ANALYSIS MODEL OF reactor system  29
RESEARCH ON LOCA DYNAMIC ANALYSIS MODEL OF REACTOR SYSTEM
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Liu, Shuai Harbin Engineering University Harbin China Science and Technology on Reactor System Design Technology Laboratory Chengdu China
The reactor system has a large scale of components. And the system dynamic analysis model for loss of coolant accidents(LOCA) contains many non-linear factors. The transient calculation analysis takes a long time and ... 详细信息
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Constructing Basic Probability Assignment Based on the Slope Correlation Degree  5
Constructing Basic Probability Assignment Based on the Slope...
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5th IEEE International Conference on Electronics technology, ICET 2022
作者: Chen, Jie Yang, Pengcheng Pu, Xiaofei Xie, Hao Wang, Jinxin Wu, Kunren Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China
DS evidence theory can be applied to deal with multi-sensor data and get reliable and accurate decision result of system's target or object due to its good measurement and reasonable description of system's un... 详细信息
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Application Verification of Wireless Sensor Network in Nuclear Power Plant  1
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6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021
作者: Deng, Zhi-Guang Wu, Qian Xiang, Mei-Qiong Dong, Chen-Long Qin, Yue Li, Zhuo-Yue Sun, Yong-Sheng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China
The application of wireless sensor network in nuclear power plant can greatly reduce the workload of nuclear power plant cable wiring, and help to improve the automation and information level of nuclear power plant. H... 详细信息
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