检索结果-内蒙古大学图书馆

Parallel multi-layer sensor fusion for pipe leak detection using multi-sensors and machine learning

Engineering Applications of Artificial Intelligence 2025年 153卷

作者： Satterlee, Nicholas Zuo, Xiaowei Lee, Chang-Whan Park, Choon-Wook Kang, John S. Department of Mechanical Engineering San Diego State University CA San DiegoCA92182 United States School of Mechanical System Design Engineering Seoul National University of Science and Technology Seoul01811 Korea Republic of Department of Undeclared Majors Kyungpook National University Daegu41566 Korea Republic of

Effective pipe leak detection is critical for maintaining the structural integrity and efficiency of water distribution systems and preventing damage such as sinkholes. Traditional leak detection methods often rely on single sensors, overlooking the advantages of multi-sensor configurations that capture diverse leak-related phenomena. To address this limitation, the study proposes an innovative machine learning-based sensor fusion approach called Parallel Multi-Layer Sensor Fusion (PMLSF), which leverages Convolutional Neural Networks (CNN) and Few-Shot Learning (FSL) to enhance leak detection. PMLSF integrates data from multiple sensors, including hydrophone, acoustic emission, and vibration sensors. The comparative analysis demonstrates that the PMLSF with multi-sensor systems substantially outperforms the CNN-based FSL (CNN-FSL) approach with single-sensor systems, achieving a leak detection accuracy of 97.1 % and leak location classification accuracy between 95.5 % and 97.4 %. Additionally, the study investigates the use of the acoustic emission sensor combined with CNN-FSL for early detection of material failure in pipes, demonstrated by a Pencil Test that achieved 92.3 % accuracy in detecting pencil breakage on the pipe. These results indicate that combination of CNN-FSL for the acoustic emission sensor and PMLSF offers a comprehensive solution for detecting and localizing existing leaks while predicting potential failures, thus laying a robust foundation for the development of reliable and efficient water distribution monitoring systems. © 2025 The Authors

关键词： Acoustic emissions

来源：评论

学校读者我要写书评

暂无评论

Secure-by-Construction Synthesis for Control systems

引用

IEEE Transactions on Automatic Control 2025年第6期70卷 4170-4177页

作者： Zhong, Bingzhuo Liu, Siyuan Caccamo, Marco Zamani, Majid Thrust of Artificial Intelligence Information Hub The Thrust of Intelligent Transportation System Hub China KTH Royal Institute of Technology Division of Decision and Control Systems Stockholm Sweden Technical University of Munich TUM School of Engineering and Design Germany University of Colorado Boulder Department of Computer Science United States Ludwig Maximilian University Department of Computer Science Munich Germany

In this note, we present the synthesis of secure-by-construction controllers that address safety and security properties simultaneously in cyber-physical systems. Our focus is on studying a specific security property called opacity, which characterizes the system's ability to maintain plausible deniability of its secret behavior in the presence of an intruder. These controllers are synthesized based on a concept of so-called (augmented) control barrier functions. We propose conditions that facilitate the construction of the desired (augmented) control barrier functions and their corresponding secure-by-construction controllers. To compute these functions, we propose an iterative scheme that leverages iterative sum-of-square programming techniques. This approach enables efficient computation of these functions, particularly for polynomial systems. Finally, we validate the effectiveness of our results through a case study of a vehicle. © 1963-2012 IEEE.

关键词： Iterative methods

来源：评论

学校读者我要写书评

暂无评论

Abstract

引用

应用力学学报 2015年第1期32卷 I0001-I0016页

作者： Feng Zhipeng Zang Fenggang Zhang Yixiong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 610213 Chengdu China

来源：评论

学校读者我要写书评

暂无评论

Analysis of contribution degree of vibration transmission of bolted structure 29

Analysis of contribution degree of vibration transmission of...

引用

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

ISBN: (纸本)9780791886359

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 vibration transmission effect is the embodiment of the coupling of various factors, so it is impossible to accurately and quantitatively evaluate the influence degree of various factors. In this paper, the influence factors of vibration between bolted plates in the form of cantilever beam are studied by numerical calculation method. The effects of friction coefficient, bolt preload, temperature and internal and external pressure on vibration characteristics are studied. Finally, the contribution of different influencing factors to vibration transmission is given. The preliminary research shows that the bolt connects the two plates into a whole structure, and its stiffness changes little with the friction coefficient, bolt preload, temperature and internal and external pressure. The natural frequency of each order increases with the increase of friction coefficient, bolt preload and internal and external pressure, decreases with the increase of temperature, and the overall trend changes little. At the same time, the bolt preload is verified by test, the difference of natural frequency under the same preload is compared and analyzed, the numerical calculation is compared with the test value, and the vibration contribution of preload is verified. © 2022 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Cantilever beams

来源：评论

学校读者我要写书评

暂无评论

The stress indices study for the pipe with trunnion welding attachment 27

The stress indices study for the pipe with trunnion welding ...

引用

27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Lu, Xifeng Bai, Xiaoming Zheng, Liangang Zhang, Rui Yuan, Feng Yuan, Yanli Huang, Qian Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China

ISBN: (纸本)9784888983051

In the nuclear power plant, the trunnion welding attachment is widely used to connect the pipe and support. According to ASME Code Cases the stress caused by the welded attachment is considered as the additional stress of the pipe. However, the calculation of the additional stress is very complex and time-consuming. A method based on the concept of stress indices is proposed in present work. To investigate the influence of size and constraint and the stress indices, the finite element analysis for pipe with different sizes trunnion welding attachment under different constraint forms are done. The stress indices are calculated for each case, respectively. Furthermore, the fitted expressions for stress indices are proposed for general case. To verify this method, an analysis according to ASME Code Case for piping with trunnion is done. The comparison of the result between present method and the ASME Code Case method show slight different. Therefore, the stress indices method for the stress analysis of pipe with trunnion welding attachment can be an alternative method for ASME Code Cases. The advantage of present method in that it simplified the analysis process by introduces the stress indices. This method is effective and practical during the design and analysis of piping system in the nuclear power plant. Copyright © 2019 by JSME

关键词： Welding

来源：评论

学校读者我要写书评

暂无评论

Model development of Uo2-zr Plate-Type fuel behavior at early phase of severe accident and molten fuel meat relocation 16

Model development of Uo2-zr Plate-Type fuel behavior at earl...

引用

16th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2015

作者： Zhuohua, Zhang Shinian, Peng Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China

ISBN: (纸本)9781510811843

According to former study on oxygen diffusion, Nb-Zr solid reaction and Uo2-zr solid reaction, models of oxidation, solid reaction in fuel meat and relocation of molten fuel meat are developed based on structure and material properties of Uo2-zr plate. The new models can supply theoretical elements for safety analysis of core assembled with dispersion plate-type fuel under severe accident.

关键词： Uranium dioxide

来源：评论

学校读者我要写书评

暂无评论

Uncertainty quantification research of reactor system under seismic load 27

Uncertainty quantification research of reactor system under ...

引用

27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Huang, Qian Xiong, Furui Bai, Xiaoming Yu, Xiaofei Zheng, Liangang Lu, Xifeng Song, Haiyang Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China

ISBN: (纸本)9784888983051

In the dynamic analysis of reactor system, the key mechanical input parameters are uncertain due to the design change, manufacturing, installation and calculation deviation, which affects the dynamic response, load distribution and final mechanical evaluation results. In order to quantify the influence of the uncertainty on seismic responses and load distribution, the uncertainty quantification of key structural input parameters of reactor system under seismic load is studied. Firstly, according to the fundamental characters of key input parameters (contact stiffness and gap among various assemblies), maximum entropy principle is adopted to construct the probability density function(PDF). Then, Markov Chain Monte Carlo technique is applied to sample according to the PDF, and the input and output data pool is constructed via finite element transient computations. According to the results, probabilistic distributions of dynamic responses caused by uncertainty from inputs parameters are evaluated and the reliability of nominal model is investigated. The studies show that the probabilistic distribution of reactor system dynamic response differs greatly with different output mechanical parameters, degrees of freedom and frequency bands. The uncertainty quantification method and process for reactor system are proposed in this paper. This method can be extended to other equipments easily. Therefore, it is an effective tools for the reliability of dynamic response. Copyright © 2018-2019 by JSME

关键词： Markov processes

来源：评论

学校读者我要写书评

暂无评论

CFD simulation of thermal hydraulic characteristics in a typical upper plenum of RPV

引用

Frontiers in Energy 2021年第4期15卷 930-945页

作者： Mingjun WANG Lianfa WANG Yingjie WANG Wenxi TIAN Jian DENG Guanghui SU Suizheng QI State Key Laboratory of Multiphase Flow in Power Engineering Department of Nuclear Science and TechnologyXi’an Jiaotong UniversityXi’an 710049China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

A comparative computational fluid dynamics(CFD)study was conducted on the three different types of pressurized water reactor(PWR)upper plenum,named TYPE 1(support columns(SCs)and control rod guide tubes(CRGTs)with two large windows),TYPE 2(SCs and CRGTs without windows),and TYPE 3(two parallel perforated barrel shells and CRGTs).First,three types of upper plenum geometry information were collected,simplified,and adopted into the BORA facility,which is a 1/5 scale system of the four-loop PWR ***,the geometry,including the upper half core,upper plenum region,and hot legs,was built using the Salome *** that,an unsteady calculation to simulate the reactor balance operation at hot full power scenario was ***,the differences of flowrate distribution at the core outlet and temperature distribution and transverse velocity inside the hot legs with different upper plenum internals were *** results suggest that TYPE 1 upper plenum internals cause the largest flowrate difference at the core outlet while TYPE 3 leads to the most even distributed *** distribution and evolution pattern of the tangential velocity inside hot legs is highly dependent on the upper plenum *** counter-rotating swirls exist inside the TYPE 1 hot leg and only one swirl revolving around the hog leg axis exist inside the TYPE 2 hot *** TYPE 3,two swirls like that of TYPE 1 rotating around the hot leg axis significantly increase the temperature homogenization *** research provides meaningful guidelines for the future optimization and design of advanced PWR upper plenum internal structures.

关键词： pressurized water reactor(PWR) upper plenum internal structures temperature distribution computational fluid dynamics(CFD)

来源：评论

学校读者我要写书评

暂无评论

THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONICS with COMSOL and RMC 29

THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONIC...

引用

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

ISBN: (纸本)9780791886366

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, the multi-physics coupling software COMSOL and 3D Monte Carlo neutron transport code RMC are coupled. The fuel rod thermo-mechanical coupling analysis module is constructed in COMSOL. RMC is innovatively wrapped as a component of COMSOL to communicate with the fuel performance module. Grid mapping algorithm is set up using COMSOL's functionality. A carefully designed segregation solver sequence is used to control the coupling process. The fine power distribution calculated by RMC is transferred to COMSOL fuel thermal calculation, and the fuel temperature and the coolant temperature and density calculated by COMSOL are transferred to RMC. In a Picard iterative way, the fuel rod lattice level neutron thermomechanical tight coupling is realized. The coupling is demonstrated in a fuel rod BOL steady state case. The fuel performance analysis is enhanced by the higher fidelity neutron flux solution. © 2022 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Iterative methods

来源：评论

学校读者我要写书评

暂无评论

Key technology of a New Potential Economical Desalination Method for Small Nuclear Power 23rd

Key Technology of a New Potential Economical Desalination Me...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Li, Siguang Gan, Yiran Li, Yi Liang, Tiebo Science and Technology on Reactor System Design Technology Laboratory Sichuan Chengdu China

ISBN: (纸本)9789811988981

With the rapid development of distributed energy, small nuclear power has been widely concerned by researchers because of its inherent advantages. Keeping circulating water in a low salinity state is an important factor in economically maintaining the system operation. Therefore, it is necessary to investigate a specialized desalination method for small nuclear power. In this paper, expert knowledge and comparative analysis were introduced to study the advantages and disadvantages of some traditional desalination methods according to the recent requirements for small nuclear power. In addition, a potential economical namely hydrate-based desalination method was discussed, the key technologies that are urgent to be solved for this method were summarized and one of these technologies, phase equilibria of gas hydrate prediction, was studied using a thermodynamic model. Results show that each traditional desalination method cannot well meet the requirements for economy, energy and environment. Referring to the national requirements for carbon emission, the hydrate-based method is much suitable for small nuclear power due to its significant advantages in the fields of economy, energy and environment. In addition, the proposed thermodynamic model shows good performance compared with the published hydrate equilibrium data. Furthermore, the kinetics of hydrate formation and decomposition is considered another key to promoting the development of hydrate-based method. Finally, we hope the solution to the above problem can provide the idea of designing small nuclear power in the future. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Desalination

来源：评论

学校读者我要写书评

暂无评论

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

请选择保存的检索档案：

请选择收藏分类：

通借通还

建议与咨询 留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

请选择保存的检索档案： 新增检索档案 确定 取消

请选择收藏分类： 新增自定义分类 确定 取消

通借通还

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

请选择保存的检索档案：

请选择收藏分类：