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International Conference on Mechatronics and Machine Vision in Practice (M2VIP)

作者： Xiaodan Yang Huilin Ren Chenchen Wu Yi Xiong Qi Ge Southern University of Science and Technology Shenzhen China School of System Design and Intelligent Manufacturing Southern University of Science and Technology Shenzhen China Guangdong Provincial Key Laboratory of Human-Augmentation and Rehabilitation Robotics in Universities Southern University of Science and Technology Shenzhen China

ISBN: (纸本)9781665431545

Flexible strain sensors have attracted much attention due to their excellent stretchability, conformability and ability to measure large deformations. These sensors have found a wide range of applications, including health tracking, human-machine interaction, and human motion monitoring. However, current mass-production methods do not support the small-batch customization of flexible strain sensors, and the additional mounting step reduces the structural integrity. This paper presents a widely accessible approach for the rapid fabrication of flexible strain sensors that are directly printed onto objects in an on-demand and reliable manner by exploring the multimaterial fused deposition modeling techniques and optimizing the composition of functional filaments. Furthermore, the feasibility and effectiveness of the proposed method are demonstrated in the development of customized, flexible strain sensors that have complex sensing patterns and geometries.

关键词： Geometry Solid modeling Tracking Three-dimensional printing Strain measurement Capacitive sensors Sensors

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Research on periodic test scheme of safety digital control system for nuclear power plant 27

Research on periodic test scheme of safety digital control s...

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

作者： Xie, Weibo Wu, Zhiqiang Zeng, Shan Li, Yutong Hu, Qingren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

The main trend in the development of the local power plant control system is to adopt digital safety DCS system with rather strong ability of self-diagnosis. Apart from the self-diagnosis, it is also necessary to carry out periodic test in certain frequency to check the potential fault within a system and to certify the completeness and effectiveness of reactor protection function. Regarding nowadays in-service or in-building power plant, there are some deficiency in the automation and simplication of the periodic test method, which still can be improved. Based on the research on the overall optimization of nuclear power plant safety DCS periodic test, an integrated and comprehensive periodic test method was put forward. This method, not only achieved a high degree of automation, supporting T2 online test, which increasing the system reliability, in order to save the cost of human and material during window phase in the overhaul life. Copyright © 2018-2019 by JSME

关键词： Nuclear power plants

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Numerical methods research and fracture failure analysis for critical crack size 27

Numerical methods research and fracture failure analysis for...

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

作者： Shi, Kaikai Yuan, Yanli Chen, Jianguo Bai, Xiaoming Zheng, Liangang Lu, Xifeng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

Safety analysis of fracture mechanics is an important part of structural integrity assessment and critical crack size is one ofmain concerns for fracture failure. From the perspective of mathematics, the calculation of critical crack size is the solving and analysis for nonlinear equation f(x)=0. About the solution of nonlinear equation, there are the bisection method, the false position method, the simple iteration method, the newton method and the secant method. For the complexity of load imposed on nuclear power equipment, there may be the multi-value phenomenon of critical crack size in analyzing fracture failure problems. Considering that the corresponding mechanical states of the shallow crack and the deep crack are different when the fracture failure occurs, the crack toughness factor needs to be considered in the fracture failure analysis of shallow cracks. Connecting the bottom head of nuclear power plant main equipment, the pipeline large break transient of accident condition and the welding research council bulletin 175, the algorithm and the convergence of multi-value phenomenon of critical size are studied. Using the crack toughness factor, the fracture failure critical crack size is deeply analyzed and discussed. The algorithm and fracture failure theory in the present study can provide the technical support for the prolonging operation life projects of nuclear power plant main equipment in future. Copyright © 2018-2019 by JSME

关键词： Numerical methods

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Analysis of PWR SBO scenarios under refueling condition using MAAP5

Analysis of PWR SBO scenarios under refueling condition usin...

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2019 Transactions of the American Nuclear Society, ANS 2019

作者： Yuan, Peng Wu, Xiaoli Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

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The defect analysis technology study of reactor pressure vessel main bolt 27

The defect analysis technology study of reactor pressure ves...

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

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

ISBN: (纸本)9784888983051

The existence of non conformances and defects are inescapable during the manufacture and in service of reactor pressure vessel (RPV). After being analyzed, most of the defects have no influence on the capability and safety of the structure if the analysis results satisfy criteria. The defects including main bolts defects, the non conformances of cladding thickness and structure dimension, structure scratch, material inclusion and so on. The typical and serious defects is main bolts defects, including thread defect, stress relaxation of bolt and the extreme case of bolt break. The results of stress, fatigue and seal performance of reactor pressure vessel will be changed considering these defects. Based on the mechanics theory and numerical simulation technique, a kind of stress, fatigue and seal performance analysis method about the defects effects is studied in this paper. The influence to the reactor pressure vessel induced by several kinds of bolt break accident is analyzed using this analysis method. Copyright © 2019 by JSME

关键词： Fatigue of materials

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Acoustic performance of fluid-filled pipe with periodic helmholtz resonator considering lateral wall elasticity

Acoustic performance of fluid-filled pipe with periodic helm...

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2019 Transactions of the American Nuclear Society, ANS 2019

作者： Zeng, Qingna Wang, Donghui Zang, Fenggang Zhang, Yixiong Science and Technology on Reactor system Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

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An automatic optimization method for nuclear piping layout and mechanical analysis 27

An automatic optimization method for nuclear piping layout a...

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

作者： Bai, Xiaoming Lu, Xifeng Zhang, Rui Shi, Kaikai Zheng, Liangang Huang, Qian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

The piping system in the nuclear power plant is extremely complex. The traditional trial method for the optimization is time-consuming and experience-dependent. Moreover, it rarely obtains the layout with best mechanical property using the trial method. In order to improve the traditional method, an automatic optimization method is proposed in present work. The genetic algorithm is employed during the mechanical analysis of piping system. In this method, both the piping layout and the piping support can be optimized concurrently. Moreover, based on the optimization method, a piping optimization theory assistant tool (POTATO) is developed. Some optimization instances in the nuclear power plant is shown in this paper. Comparing with the layout from the trial method, the one from present automatic method have more mechanical margin. The stress ratios at all the conditions are less than the limitation. Meanwhile, the time cost in present method is less than the trial method. Thus, present method is more efficient than the traditional method, and is significant for the piping layout in nuclear engineering. Copyright © 2018-2019 by JSME

关键词： Genetic algorithms

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Improvement and optimization of naspic SVDU engineering design in nuclear power plant according to NUREG0700 27

Improvement and optimization of naspic SVDU engineering desi...

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

作者： Li, Yutong Xie, Weibo Ma, Quan Zhang, Yu Zhao, Yang Hu, Qingren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

Safety Video Display Unit (SVDU) provides the interface between operator and reactor protection system (RPS).SVDU not only displays the signals and parameters which related to safety function but also support the operator to send control commands to *** a safety classified equipment and part of human machine interface (HMI), engineering design of SVDU should be addressed in plant safety with regarding to the HMI related standards. NUREG0700 is the guideline of human-system interface design, using which as a tool, a lot of improvement has been made to optimize the design of NASPIC SVDU: Display view arrangement, PAMS parameter curves, alarming etc. were improved and optimized. Then conformity analysis of NASPIC SVDU regarding NUREG0700 has been made, and equipment qualification was conducted. Finally NASPIC SVDU was prone to be in conformity with NUREG0700 and was able to achieve effective human-computer interaction. Copyright © 2018-2019 by JSME

关键词： Nuclear fuels

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The sensitivity analysis of the core lower head molten pool model based on variance decomposition 27

The sensitivity analysis of the core lower head molten pool ...

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

作者： Li, Zhigang Liu, Wei Ming, Pingzhou Pan, Junjie An, Ping Liu, Dong Lu, Wei Yu, Hongxing Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory ChengDu610041 China

ISBN: (纸本)9784888983051

The lower head molten pool model is an important model for the In Vessel Retention (IVR) effectiveness evaluation. It has the characteristics of complex relationship, many input parameters and large uncertainty. The traditional local sensitivity analysis method has the disadvantages of large amount of calculation and low efficiency when performing sensitivity analysis of complex models. Based on variance decomposition of the global sensitivity analysis method, the sensitivity analysis library(SALib) and IVR analysis code(CISER) developed by Nuclear Power Institute of china(NPIC) are adopt to analyze the sensitivity of the input parameters for four key parameters, such as the lower head wall heat flux ratio. In the paper, the sensitivity coefficient and influence tread of input parameters on key results are obtained, which provides a reference for the optimization of the lower head molten pool model and severe accident mitigation strategies. Copyright © 2018-2019 by JSME

关键词： Sensitivity analysis

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Channel Modeling and Multi-User Precoding for Tri-Polarized Holographic MIMO Communications

arXiv

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arXiv 2023年

作者： Wei, Li Huang, Chongwen Alexandropoulos, George C. Yang, Zhaohui Yang, Jun Sha, Wei E.I. Debbah, Mérouane Yuen, Chau Singapore University of Technology and Design Singapore College of Information Science and Electronic Engineering Zhejiang University China Department of Informatics and Telecommunications National and Kapodistrian University of Athens Greece Technology Innovation Institute Abu Dhabi United Arab Emirates State Key Laboratory of Mobile Network and Mobile Multimedia Technology Shenzhen China Wireless Product R&D Institute ZTE Corporation Shenzhen China CentraleSupelec University Paris-Saclay Gif-sur-Yvette France

This paper studies the exploitation of triple polarization (TP) for multi-user (MU) holographic multiple-input multiple-output surface (HMIMOS) wireless communication systems, aiming at capacity boosting without enlarging the antenna array size. We specifically consider that both the transmitter and receiver are equipped with an HMIMOS comprising compact sub-wavelength TP patch antennas. To characterize TP MU-HMIMOS systems, a TP near-field channel model is proposed using the dyadic Green's function, whose characteristics are leveraged to design a user-cluster-based precoding scheme for mitigating the cross-polarization and inter-user interference contributions. A theoretical correlation analysis for HMIMOS with infinitely small patch antennas is also presented. According to the proposed scheme, the users are assigned to one of the three polarizations, which is easy to implement, at the cost, however, of reducing the system's diversity. Our numerical results showcase that the cross-polarization channel components have a non-negligible impact on the system performance, which is efficiently eliminated with the proposed MU precoding scheme. Copyright © 2023, The Authors. All rights reserved.

关键词： Polarization

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