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8th International Conference on Energy system, Electricity, and Power, ESEP 2023

作者： Yang, Xiaohua Liu, Zhikun Fang, Weiyang Huang, Tao Liu, Jie Yang, Jinghua Ren, Changan Department of Compute Science University of South China Hengyang421001 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (数字)9781510679801

ISBN: (纸本)9781510679795

Fault severity describes the level of impact caused by a fault. In the event of a malfunction in a nuclear power plant, a vast amount of data and alarms are generated, making it challenging for operators to identify and determine the state of the power plant in a short time. If the fault severity can be effectively identified during a malfunction, it would allow the operators to respond quickly and prevent further losses. Compared to other machine learning methods, the Support Vector Machine (SVM) has superior classification capability in scenarios with limited nuclear power samples. However, if the feature representation of the SVM training sample is inadequate, resulting in similar, indistinguishable training data, it will affect the SVM's classification of fault severity. To address this issue, using the Liang-Kleeman Information Flow (IF) can characterize information transmission from a causal perspective. By introducing IF to combine features of the training data, insufficient sample features can be replaced with the IF that describes information from a causal viewpoint, thereby enhancing the SVM's accuracy in fault severity classification. This paper takes the Main Steam Line Break accident in the primary loop of the nuclear reactor as an example and conducts simulation experiments on the PCTRAN simulation platform. The experimental results show that under 5 different fault degrees, the accuracy of fault degree evaluation of SVM model combined with IF is improved. This method can effectively improve the classification accuracy of different fault severity degrees in MSLB steam flow data with similar changes. © 2024 SPIE.

关键词： Steam piping systems

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Research and development of helium-xenon Brayton cycle technology:A review

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National Science Open 2024年第6期3卷 188-218页

作者： Weixiong Chen Meihui Song Yiran Qian Hongxing Yu Junjie Yan State Key Laboratory of Multiphase Flow in Power Engineering Xi’an Jiaotong UniversityXi’an 710049China Key Laboratory of Nuclear Reactor System Design Technology Nuclear Power Institute of ChinaChengdu 610200China

Helium-xenon Brayton cycle systems have significant potential as the energy conversion system for small-scale reactors in remote land,deep-sea,and space applications due to a range of advantages,including high cycle efficiency,compact system structures,and chemical *** objective of this review is to provide a comprehensive understanding of the helium-xenon Brayton cycle system based on the projects and ***,the basic information and development history are introduced,and a series of typical designs are ***,the system configurations,cycle parameter analysis and optimization are ***,the key components are classified,such as turbine,compressor,and heat ***,the dynamic processes and control strategies are introduced in different ***,the deficiency and prospect of current research are *** review covers the representative helium-xenon Brayton cycle systems,which could provide a reference for promoting the development of energy conversion systems.

关键词： helium-xenon Brayton cycle cycle analysis heat exchanger dynamic research

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Preliminary Development of a Simulation Capability for Zircaloy Clad Ballooning in LOCA

Preliminary Development of a Simulation Capability for Zirca...

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International Conference on Water reactor Fuel Performance Meeting, WRFPM 2023

作者： Li, A. Wei Wu, B. Xiaoli State Key Laboratory for Strength and Vibration of Mechanical Structures Xi’an Jiaotong University Xi’an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789819971565

Zircaloy clad is widely known to be vulnerable to ballooning and burst in a loss-of-coolant accident (LOCA) typical of high-temperature steam environment, due to internal and external pressure difference and degraded strength. Ballooning can be detrimental in light of nuclear reactor safety. Due to the large deformation and complex constitute models in the ballooning process, detailed numerical simulation of Zircaloy clad ballooning has long been a challenge. This paper presented a preliminary Finite-Element-Method (FEM) implementation for analyzing Zircaloy clad ballooning. The developed capability can be used to predict progressive clad ballooning up to failure determined by empirical burst limit. Included physic models are currently phase transformation and high-temperature creep. Especially, anisotropic creep was considered for the α phase Zircaloy. The stress update algorithm is implicit in time integration, which ensures relatively large time increment during the simulation. The PUZRY separate effect tests were used to validate the FEM capability. The predicted time to failure (burst) is acceptable when compared with the experimental data. Besides, it was found that the effect of anisotropic coefficients is significant on the prediction of ballooning. © The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd 2024.

关键词： Loss of coolant accidents

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Research on model validation of routing protocol for UAV swarm cooperative disaster relief system

Research on model validation of routing protocol for UAV swa...

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2023 International Conference on Computer Application and Information Security, ICCAIS 2023

作者： Wei, Tonghao Liu, Jie Yang, Fei Han, Wenxing Jiang, Wei School of Computer Science/Software University of South China Hunan Hengyang China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9781510675032

In recent years, with the continuous expansion of unmanned aerial vehicle (UAV) swarm applications and the rapid development of the UAV self-organizing network system, the related security threats have also increased. In this paper, we conduct the communication model of the UAV swarm cooperative disaster relief system by verifying the security attributes of the UAV swarm cooperative disaster relief system based on the dynamic source routing (DSR) protocol and we also analyze and verify their security attributes. Finally, we propose a novel scheme to model, characterize, and verify the security attributes of the UAV swarm communication networks. It provides a formal analysis and verification method for verifying the security attributes of self-organized network systems, simplifying a series of challenging verification processes that come with demonstrating the security attributes of the system through simulation experiments. © 2024 SPIE.

关键词： Formal verification

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Improvement of multi-functional properties by fabricating micro-pillar arrays structures on zirconium alloy surface

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Science China(Technological Sciences) 2022年第6期65卷 1243-1252页

作者： WANG XiaoLiang WANG HaoYu LIU YongDa QI Min REN QuanYao XU Jie SHAN DeBin GUO Bin Key Laboratory of Micro-systems and Micro-structures Manufacturing of Ministry of Education Harbin Institute of TechnologyHarbin 150080China School of Materials Science and Engineering Harbin Institute of TechnologyHarbin 150001China Science and Technology on Reactor System Design Technology Laboratory Chengdu 610041China

Although using the microstructure of a surface to enhance specific functions has immense applicability in numerous fields,few studies have been conducted on the multi-functional properties of nuclear fuel elements in harsh *** this study,surfaces with zirconium alloy micro-pillar arrays were prepared using micro-milling and ultraviolet nanosecond laser technology,and their functional properties such as the wettability,structural stability,and corrosion resistance were *** was found that the geometric dimension of the micro-pillar arrays prepared using these two methods could meet the design requirements,but the micro-milling process had the best dimensional ***-nano multi-scale structures were obtained by laser ***,these multi-scale structures exhibited weak structural stability,and the nanostructures were easily *** contrast,the micro-pillar arrays manufactured using micro-milling were confirmed to have better structural stability and corrosion *** one hand,the area mass loss of the micro-milled structure was lower than that of a flat surface after experiencing high-pressure fluid scouring at 8 and 38 m/*** the other hand,the oxidation weight gain of the surface with the micro-milled structure was lower than that of a flat surface,and the oxide film was 22.5% thinner after 100 days of deionized water corrosion at 360℃ and 18.7 MPa.

关键词： zirconium alloy micro-pillar arrays wettability structural stability corrosion

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design of Static Semantic Analyzer for Code Generator Applied in Safety-Level I&C of NPPs 7th

Design of Static Semantic Analyzer for Code Generator Applie...

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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Lan, Lin Wang, Gang Tu, Jun Li, Zhe Huang, Di Zhang, Jia-Cheng Jiang, Wei Nuclear Power Institute of China Institute of Reactor Operation and Application Leshan Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of the China Chengdu Sichuan China

ISBN: (纸本)9789819934546

In the nuclear safety level I&C (Instrument and Control) area, the code generator plays an important role in developing the application software. The main function of the code generator is to translate the Lustre program corresponding to the graphical control algorithm into C code. Therefore, the reliability and quality of the code generator will directly affect the safe and reliable operation of nuclear power plants. In order to ensure the correctness of Lustre code, a static semantic analyzer is designed and developed to find the errors in source Lustre code. Its function is to check the correctness of the input source Lustre code, including identifier-checking declarations, identifier-checking programs, type-checking expressions and equations, clock-checking expressions and equations. According to the characteristics of Lustre language, the static semantic analyzer is designed and developed, and its function and correctness are verified by a large number of test cases. In this paper, mainly introducing the design and implementation of the static semantic analyzer. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Semantics

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A Transformer-based Time Series Prediction Model with Contrastive Learning for Nuclear Power system State Monitoring 15

A Transformer-based Time Series Prediction Model with Contra...

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15th IEEE Global Reliability and Prognostics and Health Management Conference, PHM-Beijing 2024

作者： Gou, Pengfei Zheng, Daiwei Tang, Lei Liu, Mengjuan School of Information and Software Engineering University of Electronic Science and Technology of China UESTC Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China NPIC Chengdu China

ISBN: (纸本)9798350354010

Prognostics and Health Management (PHM) is currently the mainstream solution for the condition monitoring and maintenance of industrial systems. In PHM, the system condition is monitored by monitoring the operational status parameters of the system to diagnose equipment faults, predict the remaining useful life, etc. Utilizing sequential operational status parameters to complete prediction and classification tasks is usually modeled as a time series processing task. Therefore, a high-performance time series prediction model is crucial for PHM. This paper focuses on the use of time series prediction models to achieve the prediction of key state parameters of the nuclear power system. However, there are still some challenges when directly applying existing time series prediction models to industrial systems. First, obtaining operational data on the nuclear power system is relatively difficult, resulting in a small amount of training data, which causes many models to face the risk of insufficient training or overfitting. Second, most of the existing time series prediction models are composed of high- and low-frequency decoupling modules, while the operational data of nuclear power systems often have fewer high-frequency components, making it difficult for many existing SOTA models to achieve good results. In order to address these challenges, we have developed a Transformer-based time series prediction model with contrastive learning for monitoring the status of nuclear power systems. We evaluated the new model on three nuclear power simulation datasets and four power transformer datasets. The experimental results show that the new model's performance is superior to baseline models. We also proved the effectiveness of our improvement through ablation experiments. © 2024 IEEE.

关键词： Prediction models

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Research on Cylindrical Linear Induction Motor for Drive Mechanism 14

Research on Cylindrical Linear Induction Motor for Drive Mec...

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14th International Symposium on Linear Drivers for Industry Applications, LDIA 2023

作者： Niu, Xu Yu, Tianda Zhang, Lu Li, Qingzhao Huang, Siyu Liu, Yanting Wu, Hao Tang, Yuan School of Electrical Engineering Harbin Institute of Technology Harbin China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9798350329612

The control rod drive mechanism (CRDM) is a kind of servo mechanism for the reactor control system of the nuclear power plant. This paper presents a cylindrical linear induction motor suitable for the CRDM. First, the structure of the CRDM is introduced. Second, the relationship between the main dimensions and the electromagnetic load is derived. Third, the influence of materials of the mover shielding shell, speed, and electromagnetic parameters on the lifting force is analyzed by the finite-element method (FEM). Meanwhile, the steady-state temperature of each component of the CRDM is obtained. Finally, a scaled-down prototype is manufactured to verify the rationality of the design. The test results show that the FEM results are consistent with the experimental results, and the essential functions such as lifting, lower insertion, and maintenance can be realized. © 2023 IEEE.

关键词： Finite element method

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Characteristic Analysis of a Cylindrical Linear Motor for Drive Mechanism 26

Characteristic Analysis of a Cylindrical Linear Motor for Dr...

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26th International Conference on Electrical Machines and systems, ICEMS 2023

作者： Niu, Xu Yu, Tianda Zhang, Lu Zhang, He Harbin Institute of Technology School of Electrical Engineering Harbin China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9798350317589

The control rod drive mechanism (CRDM) is a critical device in nuclear plants. This paper proposes a kind of CRDM applying the cylindrical linear induction motor (CLIM). First, the structure and the working principle are introduced. Second, the finite-element method (FEM) is applied to analyze the electromagnetic characteristics of CRDM. The lifting force variation curves with different electromagnetic and structural parameters are obtained. Third, the thermal analysis is carried out by FEM. The steady-state thermal distribution and temperature of each component of CRDM are obtained. All the above results show that the proposed CRDM can meet the design criteria and such functions as rising, falling, and holding still. © 2023 IEEE.

关键词： Finite element method

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STUDY ON HYDROGEN RISK VENTING MITIGATION MEASURE OF SMALL STEEL CONTAINMENT DURING SEVERE ACCIDENT 29

STUDY ON HYDROGEN RISK VENTING MITIGATION MEASURE OF SMALL S...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Zou, Zhiqiang Zhang, Hang Zhang, Ming Peng, Huanhuan Xu, Youyou Deng, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886465

The hydrogen risk in small steel containment is one of the most important safety problems of small modular reactor (SMR), effective measures need to be taken to mitigate the risk of high concentration hydrogen in a small free volume during severe accidents. In the early stage of a severe accident caused by a loss of coolant accident, the pressure in the containment may rise rapidly, probably triggering the immediate venting of the containment, which can protect the integrity of the containment in the stage of pressure rise in the short term. In the later stage of a severe accident, the generation of hydrogen from reactor core may cause hydrogen combustion or even explosion, which may cause the possibility of overpressure in the containment. In this paper, Computational Fluid Dynamics (CFD) GASFLOW-MPI code is used to analyze the effect of containment venting measures on hydrogen risk in small steel containment of SMR during severe accident initiated by direct vessel injection line break loss-of-coolant. The analysis results show that the venting action can effectively depressurize the containment, the larger the area of the venting pipe is, the more obvious the depressurization effect is. However, hydrogen cannot be effectively discharged in the middle and later stage of the accident, so the risk of hydrogen cannot be completely eliminated, and the possibility of flame acceleration in containment cannot be ruled out for the reason that the negative pressure generated by water vapor condensation will suck in the air outside the containment and form a combustible gas cloud again. Copyright © 2022 by ASME.

关键词： Risk assessment

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