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Tool wear parameters identification in precision milling using a hybrid model combining cutting forces analytical model and Gaussian process regression method*

Tool wear parameters identification in precision milling usi...

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

作者： Shengqiang Zhao Lin Zhou Hao Sun Fangyu Peng Rong Yan Teng Zhang National NC System Engineering Research Center School of Mechanical Science and Engineering Huazhong University of Science and Technology Wuhan China Wuhan Digital Design and Manufacturing Innovation Center Co. Ltd China Wuhan China State Key Laboratory of Digital Manufacturing Equipment and Technology School of Mechanical Science and Engineering Huazhong University of Science and Technology Wuhan China

ISBN: (纸本)9781665431545

In precision milling, tool wear has a significant impact on tool life prediction, machining accuracy and surface quality evaluation of workpiece. Tool wear pattern generally includes the increase of the tool flank wear width, as well as the expansion of the edge radius in precision process. Therefore, two tool wear parameters in precision milling have been generalized in this paper. The milling cutting force analytical model considering tool wear is set up to generate the data related to cutting force and tool wear parameters, which can be used as the dataset to construct and train the Gaussian process regression model. Finally, the trained regression model can output the prediction of tool flank wear width and edge radius as measured cutting forces treated as input values, which is helpful to realize the online monitoring of tool wear in the processing site environment. Consequently, the average relative prediction errors of tool flank wear width and edge radius are controlled within 2%, with the prediction time within 100ms.

关键词： Training Analytical models Parameter estimation Machine learning algorithms Force Milling Gaussian processes

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Pipe Routing of reactor Based on Adaptive A* Algorithm Combined With Genetic Algorithm

Pipe Routing of Reactor Based on Adaptive A* Algorithm Combi...

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Chinese Automation Congress (CAC)

作者： Weihang Lv Na Qin Xinyu Zhao Peng Yuan Jie Huang School of Electrical Engineering Southwest Jiaotong University Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (数字)9781728176871

ISBN: (纸本)9781728176888

To solve the complex 3-D space pipe routing problem, an algorithm framework combining genetic algorithm and adaptive A * algorithm (AAGA) is proposed. The initial population of the genetic algorithm is generated using the adaptive A * algorithm combined with the concept of intermediate join points, this method is also used in the generation of sub-paths in the crossover and mutation operations of genetic algorithms. On the one hand, this method improves the quality of the initial population and speeds up the optimization of genetic algorithm, on the other hand, it solves the problem that the genetic algorithm combined with the traditional A * algorithm (AGA) is prone to redundant inflection points. Finally, on the premise of ensuring pipeline connectivity, pipeline length and number of inflection points, the constraints of pipeline center of gravity and minimum bending radius are added to carry out simulation experiments. Simulation results show that the AAGA has better performance than adaptive A * algorithm and AGA.

关键词： Pipelines Genetic algorithms Layout Statistics Sociology Biological cells Routing

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Application of feedforward predictive control in DC furnace coordination system

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Journal of Physics: Conference Series 2021年第1期1780卷

作者： Zhiguang DENG HE Zhengxi ZHU Biwei ZHU Jialiang LV Xin WU Qian National Key Labortory of Science and Technology on Reactor System Design Technology Chengdu610213China

In order to solve the control difficulties such as large dynamic delay, serious coupling between machine and furnace and strong nonlinear, the feedforward and feedback predictive control is proposed to control the coordinated system on the basis of multi-model predictive control, and the static feedforward part designs the feed line feedforward of coal quantity against coal quality disturbance on the basis of the accurate balance of energy. Thus, the reference total fuel quantity under the target load instruction is determined, and the dynamic part fully considers the dynamic compensation of the unit energy storage, gives a certain overshoot fuel quantity to the boiler regulation, speeds up its response, and ensures the rapidity of the unit. The real-time simulation results of virtual DPU (Distributed Processing Unit) show that the designed feedforward-feedback predictive control can quickly respond to load change, improve the resistance to fuel disturbance, reduce the fluctuation of main steam pressure, and better ensure the safe, economic and stable operation of the coordination system.

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Hydrogen risk analysis of a large pressurized water reactor using hydragon code 27

Hydrogen risk analysis of a large pressurized water reactor ...

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

作者： Zhang, Xiaolong Yu, Jiyang Huang, Tao Jiang, Guangming Zou, Zhiqiang Department of Engineering Physics Tsinghua University Beijing100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888983051

This paper presents the hydrogen risk analysis of a large Pressurized Water reactor (PWR) undergoing a severe accident using the HYDRAGON code. The code has been developed by the Department of Engineering Physics, Tsinghua University, as a hydrogen risk analysis software specialized for containment building of nuclear reactor power plants. The chemical interaction between zirconium cladding of the fuel rods and overheated coolant may release hydrogen when severe accidents occur in PWRs. The hydrogen mixed with air existing in containment may jeopardize the integrity of containment building if the flammable mixture explodes. In order to mitigate the hydrogen risk, many nuclear power plants install the Passive Autocatalytic Recombiners (PARs) that allow hydrogen and oxygen react chemically at low temperature without any sights of flame. Recombiners remove hydrogen and thereby prevent explosions. This work simulated the gas diffusion behaviors during the accident in the containment of a large PWR. The simulations obtained spatial concentration distribution of various gas species including hydrogen, oxygen, steam and nitrogen and several key parameters that are required to complete hydrogen burning and explosion investigation. Sensitivity analyses of recombiners' quantity and positions and hydrogen discharge intensity provides the reference for hydrogen mitigation measure design in the containment. The results demonstrate that the number of recombiners rather than positions has stronger influences on hydrogen mitigation. Since the installation position reflects less sensitivity, the recombiners could be arranged as higher as possible if necessary. Copyright © 2018-2019 by JSME

关键词： Hydrogen

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Analysis and verification of burnup algorithm in reactor 27

Analysis and verification of burnup algorithm in reactor

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

作者： Hu, Yuying Luo, Qi Yao, Dong Yu, Yingrui Liao, Hongkuan Zhou, Bingyan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

Burnup algorithm analysis is an important part of the physical calculation in reactor. The computing accuracy of burnup algorithms is directly related to the correctness of the whole physical calculation. Due to the difference from the rates and lives of varieties of nuclides, burnup matrices are always sparse rigid exponential ones. At present, methods to solve exponential matrices are divided into two types, numerical methods and analytical methods. Besides, numerical methods conclude series methods, ordinary differential equation methods, polynomial methods, matrix decomposition methods and so on. In this study, some common methods to solve burnup matrices are introduced, such as Chebyshev Rational Approximation Method(CRAM), Krylov Subspace Method, Pade Approximation Method and Transmutation Trajectory Analysis(TTA). Analysis and verification for microscopic point-depletion calculation are carried out with two typical burnup chains. One of the burnup chains for verification is a decay chain of neptunium-237(237Np), which contains 13 nuclides. The other chain is an actinide nuclide reaction chain, including 25 nuclides from decay and neutron capture and 9 nuclides from fission. Because there is no close annual chain in the burnup chains used in verification, the results of using Transmutation Trajectory Analysis were thought to be accurate, and it has been used as the benchmark for comparative analysis of other methods. The final result shows, Chebyshev Rational Approximation Method has advantages in calculation accuracy and simplicity, and it is suitable to be used in large burnup calculations. Copyright © 2018-2019 by JSME

关键词： Isotopes

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Towards Secure Semantic Transmission In the Era of GenAI: A Diffusion-based Framework

arXiv

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arXiv 2025年

作者： He, Boxiang Chen, Zihan Luo, Junshan Liu, Chuanhong Wang, Shilian Wang, Fanggang Quek, Tony Q.S. College of Electronic Science and Technology National University of Defense Technology Changsha410073 China Information Systems Technology and Design Singapore University of Technology and Design Singapore Beijing Key Laboratory of Network System Architecture and Convergence School of Information and Communication Engineering Beijing University of Posts and Telecommunications Beijing100876 China School of Electronic and Information Engineering Beijing Jiaotong University Beijing100044 China

Semantic communication, due to its focus on the transmitting meaning rather than the raw bit data, poses unique security challenges compared to the traditional communication systems. In particular, semantic communication systems are vulnerable to the malicious attacks that focus on the semantic layer, with the intention of understanding or distorting the intended meaning of the transmitted privacy data. Diffusion models, a class of generative artificial intelligence (GenAI), are well-suited for ensuring data security to attack. Through iteratively adding and then removing noise, diffusion models can generate meaningful information despite the presence of the unknown noise. This article proposes a diffusion-based framework to enhance the security of semantic transmission for the attacks including eavesdropping and jamming. Specifically, the proposed framework incorporates both the artificial noise and natural channel noise into the forward process of the diffusion models during the semantic transmission, with the reverse process used to remove noise at the legitimate receiver. In the eavesdropping scenarios, the artificial noise is the friendly noise designed to prevent semantic eavesdropping. In the jamming scenarios, the artificial noise is the malicious jamming generated by the jammer, which disrupts the semantic transmission. The case studies show that the proposed diffusion-based framework is promising in securing the semantic transmission. We also consolidate several broad research directions associated with the proposed framework. Copyright © 2025, The Authors. All rights reserved.

关键词： Electroosmosis

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High-accuracy time synchronization method in highly reliable fiber-channel communication system 27

High-accuracy time synchronization method in highly reliable...

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

作者： Chen, Qi Jiang, Wei Tu, Xiaodong Yu, Bo Liu, Mingxing Zhang, Xu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China School of Information and Communication Engineering University of Electronic Science and Technology of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

Accompanied with strict requirements on accuracy and determinacy in nuclear power industrial safety Digital Control system (DCS), time-triggered technology has been used in Ethernet widely, while another network protocol, Fiber-Channel (FC) protocol which is popular in avionic electronic systems with hyper reliability in port to port communication stands still, even though the optical fiber cable is quite adopted by other protocols like Ethernet. One important reason is the lack of the capability to handling time sensitive tasks in FC protocol itself. In order to bring Fiber-Channel protocol into real-time applications, like safety DCS for nuclear industry, with the situation that there are pretty few researches on the time synchronization in FC protocol, this paper makes fundamental research on the solution to achieve high-accuracy time synchronization in FC protocol networks, which has been proved a vital important step to realize real time communication according to Time-Triggered Ethernet (TTE)(H. Kopetz al, 2005). By analyzing current Fiber-Channel network time communication strategies and demo-boards testing, this paper designs a method to achieve the same level or better synchronization accuracy in FC network with that in TTE, which figures out a new direction in this blank field of time synchronization in FC protocol. Furthermore, this method only asks for few resources and slight modifications on current communications for future development and improvement. Copyright © 2018-2019 by JSME

关键词： Accident prevention

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A systematic Review of Multi-Sensor Information Fusion for Equipment Fault Diagnosis

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IEEE Transactions on Instrumentation and Measurement 2025年

作者： Lin, Tantao Ren, Zhijun Zhu, Linbo Zhu, Yongsheng Feng, Ke Ding, Weiping Yan, Ke Beer, Michael Xi'an Jiaotong University Key Laboratory of Education Ministry for Modern Design & Rotor-Bearing System Xi'an710049 China Xi'an Jiaotong University Frontier Institute of Science and Technology Xi'an710049 China Xi'an Jiaotong University School of School of Chemical Engineering and Technology Xi'an710049 China Xi'an Jiaotong University School of Mechanical Engineering Xi'an710049 China Nantong University School of Artificial Intelligence and Computer Science Nantong226019 China City University of Macau Faculty of Data Science Macau999078 China Leibniz University Institute for Risk and Reliability Hannover30167 Germany University of Liverpool Department of Civil and Environmental Engineering LiverpoolL69 3BX United Kingdom Tongji University International Joint Research Center for Resilient Infrastructure International Joint Research Center for Engineering Reliability and Stochastic Mechanics Shanghai200092 China

In contrast to fault diagnosis relying solely on a single sensor, the method of multi-sensor information fusion for fault diagnosis (MSIFFD) broadens the spectrum of available information sources. It is renowned for its high accuracy and reliability, traits that have attracted growing attention within the research community and led to the generation of a substantial body of publications. However, there is currently a lack of a comprehensive and systematic review in this domain. Thereby, this review aims to thoroughly explore all research achievements in the field of MSIFFD. At the outset, an analysis is undertaken to delineate the fusion level of multi-sensor information, with a specific focus on its location and types of inputs and outputs within the information flow. Subsequently, an examination of the six primary fundamental operations for amalgamating multi-sensor information is undertaken to clarify the motivations and processes involved in information fusion across various operations. Following this, factors influencing fusion diagnostics and strategies aimed at improving their performance are examined to explore approaches for enhancing fusion accuracy. The subsequent sections delve into the analysis of sensor types and application scenarios, providing a reference guide for practical applications. Finally, this review outlines potential future challenges in the field of MSIFFD and provides a range of recommendations and possible solutions for consideration. © 1963-2012 IEEE.

关键词： Information fusion

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Research about the influence of passive residual heat removal system on SGTR accident 27

Research about the influence of passive residual heat remova...

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

作者： Wu, Yirui Shan, Jianqiang Xu, Tao Ma, Haifu Yang, Junyun Yu, Hong Wang, Junlong School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi Province China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan Province China

ISBN: (纸本)9784888983051

Since the passive safety system turns out to be a desirable method to achieve simplification and increase the reliability of the performance of essential safety functions, passive technology with inherent safety features has been generally applied to the design of advanced nuclear power plant. The PWR (pressurized water reactor) NPP (nuclear power plant) in this paper is a kind of mature pressurized water plants in China, and is proposed to be improved with some passive systems to enhance safety performance. The proposed and adapted passive safety systems for this PWR power plant in this paper contain: (1) the RMT (reactor makeup tank);(2) the A-ACC (advanced accumulators);(3) the IRWST (in-containment refueling water storage tank);(4) the PDS (passive depressurization system);(5) the PRHRS (passive residual heat removal system), which is installed on the reactor coolant system (RCS) loop. In this research, the behaviors of passive safety systems are studied and transient characteristics of the primary and secondary side of the reactor during the Steam Generator Tube Rupture (SGTR) accident are investigated using the best-estimate transient simulation code Relap5/MOD3.3. Results reported in this paper indicate that making use of passive safety systems especially the PRHRS could ensure reactor safety during the SGTR accident. Copyright © 2018-2019 by JSME

关键词： Pressurized water reactors

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Comparison of SGTR accident with two different passive residual heat removal systems 27

Comparison of SGTR accident with two different passive resid...

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

作者： Wu, Yirui Shan, Jianqiang Xu, Tao Ma, Haifu Yang, Junyun Yu, Hong Wang, Junlong Deng, Yaxin School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi Province China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan Province China

ISBN: (纸本)9784888983051

Since the passive safety system turns out to be a desirable method to achieve simplification and increase the reliability of the performance of essential safety functions, passive technology has been generally applied to the design of advanced nuclear power plant. The traditional generation II+ nuclearpower plant is proposed to be improved with some passive systems to enhance safety performance. There are two series of passive safety systems for this kind of nuclear power plant in this paper, one of them contains: (1) the RMT (reactor makeup tank);(2) the A-ACC (advanced accumulators);(3) the IRWST (in-containment refueling water storage tank);(4) the PDS (passive depressurization system);and (5) the PRHRS (passive residual heat removal system), which is installed on the reactor coolant system (RCS) loop;the other contains:(1) the RMT (reactor makeup tank);(2) the A-ACC (advanced accumulators);(3) the IRWST (in-containment refueling water storage tank);(4) the PDS (passive depressurization system);(5) the PEFS(passive emergency feed water system), which is installed on the secondary side of SGs. In this research, the transient characteristics of SGTR accident with the two different passive residual heat removal systems which are PRHRS and PEFS is investigated using the best-estimate transient simulation code Relap5/MOD3.3. The calculation results show that both of PRHRS and PEFS could remove the decay heat from the primary loop efficiently to ensure the reactor safety and reduce the radioactive leakage to mitigate the accident impact during the SGTR accident. Due to the significant cooling effect of PRHRS and PEFS, the water level of broken SG would not be overfilled in both conditions, which is different with the SGTR accident of traditionalgeneration II+nuclear power plant. Compared with the PEFS, the PRHRS performed better in cooling efficiency, long-term cooling performance, reducing radioactive leakage capacity and mitigating accident effect. Copyright © 2018-2

关键词： Nuclear power plants

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