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13th International Conference on Electronics, Communications and Networks, CECNet 2023

作者： Liu, Jie Qi, Xiaodi Wu, Zhiqiang Jiang, Wei Chen, Zhi Jian, Yifan Wen, Juan School of Computer/Software University of South China China Laboratory of Nuclear Reactor System Design Technology China Nuclear Power Research and Design Institute China

ISBN: (纸本)9781643684802

The collection of nuclear power plants operating data is the basis for subsequent fault diagnosis and obtaining the operating status of nuclear power plants, but equipment failures and external interference will lead to missing operating monitoring data, which will reduce the quality of the data and thus reduce the accuracy of the subsequent analysis results. To solve this problem, this paper utilizes the fact that nuclear power plants have accumulated a large amount of operational data and researches the method of generating adversarial imputation network (GAIN)-based imputation method for missing values of nuclear power plants' operational data. The generator in the model estimates the missing values by learning the distribution of the true values, and the discriminator in the model discriminates which values are true and which are generated with the help of a hint matrix. The hint reveals partial information about the missing original samples to the discriminator, which the discriminator uses to focus its attention on the quality of the imputation of particular data values. Finally, a training set and a test set were constructed for comparative experiments on the PCTran simulation platform by simulating the operational data of the AP1000 as an example. The experimental results demonstrate that the investigated algorithm achieves lower root mean square error (RMSE), verifying the feasibility and accuracy of the method. © 2024 The authors and IOS Press.

关键词： Nuclear power plants

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Input-to-state stability and gain computation for networked control systems

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Control Theory and technology 2023年第3期21卷 292-300页

作者： Qianqian Cai Minyue Fu School of Automation Guangdong University of TechnologyGuangzhou 510006GuangdongChina School of System Design and Intelligent Manufacturing Southern University of Science and TechnologyShenzhen 518055GuangdongChina

This paper studies the stability problem for networked control systems.A general result,called network gain theorem,is introduced to determine the input-to-state stability(ISS)for interconnected nonlinear *** show how this result generalises the previously known small gain theorem and cyclic small gain theorem for *** the case of linear networked systems,a complete characterisation of the stability condition is provided,together with two distributed algorithms for computing the network gain:the classical Jacobi iterations and a message-passing *** the case of nonlinear networked systems,characterisation of the ISS condition can be done using M-functions,and Jacobi iterations can be used to compute the network gain.

关键词： Small gain theorem-Networked systems Input-to-state stability Robust stability Distributed algorithm

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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

ISBN: (纸本)9789811988981

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 regulatory requirements. Based on the measurement results of 131I source term of several units in nuclear power plant A during shutdown, this paper study the variation law of 131I source term in the transient process of shutdown, analyzes the causes of 131I peak release, calculates the 131I release rate in the transient process, and obtains the following conclusions: 1) the 131I release rate based on the measured value is significantly lower than that used in the current safety analysis;2) The larger the fuel rod break size, the smaller the peak factor of 131I in the primary circuit during transient. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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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

ISBN: (纸本)9789811911804

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 into embedded software platform of NASPIC after compiled by a common C compiler. Therefore, the credibility of the code generator is directly related to the safety of nuclear power plant operation. At present, the methods which are used to guarantee the credibility of code generators mainly include test and V&V. However, the formal method describes the software system from a mathematical point of view and verifies its correctness of translation processes, which can improve the credibility of the code generator to the greatest extent. Based on the formal method and compilation technology, this paper introduces the design and implement of code generator for safety I&C software. A initial test has been performed to check the requirement of nuclear I&C software development. The test results show that the code generator can translate Lustre program into C program. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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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

ISBN: (纸本)9780791886472

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 the convergence is difficult to guarantee. In this paper, two different analysis models (complete three-loop model and single-loop model) of the reactor loop system are established for comparative analysis. The analysis shows that the calculation error of the main position load in the two different model is within 10%. The decoupling influence of the surge tube and the reactor inlet and outlet on the system dynamic characteristics is within an acceptable range. When the single-loop model is used, it is necessary to decouple the reactor pressure vessel and pressurizer. And the simplified boundary is adapted to simulate its effect on the whole loop. The single-loop dynamic analysis model based on the decoupling criterion can greatly reduce the calculation scale and meet the calculation accuracy, which can be used to calculate the LOCA dynamic characteristics of the reactor system quickly. The model can also be used for seismic analysis of reactor system. And using this model for reactor system dynamic analysis can greatly improve the calculation efficiency. Copyright © 2022 by ASME.

关键词： Loss of coolant accidents

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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

ISBN: (纸本)9781665485081

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 uncertainty. In practical application field, DS evidence theory is achieved by two steps, one is the acquisition of the basic probability assignment function (BPA), and the other is the synthesis of multiple evidences that is obtained from multi-sensor data. The existing relevant literatures mainly solve the combination problem of conflict evidences, while lack of systematic research on the acquisition of BPA. In this paper, we focus on the discussion and innovation of the acquisition of BPA. BPA in DS evidence theory is the basic unit to describe the uncertainty of the system and evidences, which fundamentally determines its superiority with respect to probability theory and Bayesian reasoning. Getting a reasonable and effective BPA is the premise of the application of DS evidence theory. Traditional BPA acquisition methods have the limitations like absent priori knowledge and low acquisition accuracy. Aiming to solve the technical difficulties of traditional methods, we put forward a new BPA acquisition algorithm based on the slope correlative degree. The novel algorithm proposed in this paper successfully realizes the reliable descriptions of system's uncertainty, which is conducive to product the accurate BPAs and the precise fusion results. Experimental results and analyses demonstrate that the innovative algorithm can not only produce reasonable BPAs, which can better fit the sensors' monitoring data, but also expand the gap between the support degree of different propositions in BPA, which is more beneficial to the synthesis of evidences and the decision fusion of the system. Thus, the novel BPA acquisition algorithm has great application value and research significance. © 2022 IEEE.

关键词： Uncertainty analysis

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Simulation Method for Multiscale Failure of Optocoupler Based on Aging of Solder Layer in Photovoltaic MOSFET 2

Simulation Method for Multiscale Failure of Optocoupler Base...

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2nd IEEE International Power Electronics and Application Symposium, PEAS 2023

作者： Chen, Xuan Yao, Ran Li, Hui Lai, Wei Min, Yuan Yang, Cheng Duan, Zeyu Chen, Siyu Xing, Zhen Chongqing University State Key Laboratory of Power Transmission Equipment Technology Chongqing China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9798350313765

This paper presents a simulation method for investigating the failure of optocoupler equipment (OCEP) in multi-physical fields. The method is based on the aging of the solder layer of the photosensitive field-effect tube (PFET) and aims to analyze the performance degradation of the PFET. Firstly, a comprehensive multi-physical field model of the OCEP is developed using the actual structure of the CT test OCEP, taking into account the conductivity of the chip. Next, an OCEP failure simulation method is proposed, which takes into account the shedding of the PFET solder layer caused by the failure mechanism of the OCEP. Finally, the simulation results demonstrate that the degree of solder layer shedding reaches 70%, resulting in the failure of the OCEP. © 2023 IEEE.

关键词： multi-physics modeling optocoupler solder layer failure

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Electrolytic Failure Modeling of Aluminum Electrolytic Capacitor by Finite Element Method 2

Electrolytic Failure Modeling of Aluminum Electrolytic Capac...

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2nd IEEE International Power Electronics and Application Symposium, PEAS 2023

作者： Chen, Xinrui Yao, Ran Li, Hui Lai, Wei Min, Yuan Yang, Cheng Duan, Zeyu Chen, Siyu Chongqing University State Key Laboratory of Power Transmission Equipment Technology Chongqing China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9798350313765

The failure rate of aluminum electrolytic capacitor (AEC) is high in power electronic systems. Due to the complex structure of AEC, it is difficult to establish an actual model, so experiments are the common way to analyze the failure of AEC. Thus, this paper proposes a finite element method (FEM) for AEC considering electrolytic failure. Firstly, the mechanism of electrolytic failure and changes of characteristic parameters in the AEC are elucidated. Secondly, an equivalent finite element model is established to simulate and analyze the electrolytic failure of AEC. Finally, the effectiveness of the proposed AEC FEM method is verified through capacitor aging experiments. © 2023 IEEE.

关键词： aluminum electrolytic capacitor (AEC) electrolytic failure finite element method (FEM)

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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

ISBN: (数字)9789811911811

ISBN: (纸本)9789811911804

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. However, its application also faces the constraints of strong electromagnetic interference, high temperature and other special complex nuclear environment, especially the narrow multi metal enclosed space of nuclear power plant cabin, which brings challenges to the application of wireless sensor. Based on the Lora wireless protocol, this paper studies the low-power selection of wireless sensor and MCU, sleep / wake-up low-power mechanism, dual star adaptive frequency hopping anti-interference, frequency division and time division multi node real-time communication and other aspects. On this basis, the prototype is developed, and the functional test, high and low temperature test, electromagnetic compatibility test and bench test are carried out. The feasibility of wireless sensor application in nuclear power plant is preliminarily verified, which lays a foundation for further application. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Wireless sensor networks

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Research on Switch Signal Transmission system Based on Optical Fiber 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： Xiang, Mei-Qiong Zhu, Jia-Liang He, Zheng-Xi Deng, Zhi-Guang Dong, Chen-Long Li, Zhuo-Yue Sun, Yong-Sheng Peng, Ye-Shun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (数字)9789811911811

ISBN: (纸本)9789811911804

Nuclear power plants need to transmit a large number of switch signals, while traditional electrical transmission of switch signals requires a large number of cables, which makes it difficult to realize self-inspection of transmission path faults and is vulnerable to electromagnetic interference. In view of the needs of a large number of switch signal transmission and the shortcomings of traditional electrical methods, this paper developed two sets of switch signal transmission systems based on optical fiber, which realized the simultaneous transmission of 16 channels and 2 channels of switch signals on one optical fiber, and had the function of transmission path fault self-checking. It has the advantages of wide frequency response range, small transmission delay, high reliability and strong environmental tolerance, and has broad application prospects. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Optical fibers

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