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In-situ TEM observation of the evolution of helium bubbles in Mo during He^(+)irradiation and post-irradiation annealing

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Chinese Physics B 2021年第8期30卷 102-112页

作者： Yi-Peng Li Guang Ran Xin-Yi Liu Xi Qiu Qing Han Wen-Jie Li Yi-Jia Guo College of Energy Xiamen UniversityXiamen 361102China Fujian Research Center for Nuclear Engineering Xiamen 361102China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

The evolution of helium bubbles in purity Mo was investigated by in-situ transmission electron microscopy(TEM)during 30 keV He^(+)irradiation(at 673 K and 1173 K)and post-irradiation annealing(after 30 keV He^(+)irradiation with the fluence of 5.74×10^(16)He^(+)/cm^(2)at 673 K).Both He^(+)irradiation and subsequently annealing induced the initiation,aggregation,and growth of helium *** had a significant effect on the initiation and evolution of helium *** higher the irradiation temperature was,the larger the bubble size at the same irradiation fluence would *** 1173 K irradiation,helium bubbles nucleated and grew preferentially at grain boundaries and showed super large size,which would induce the formation of *** the same time,the geometry of helium bubbles changed from sphericity to *** polyhedral bubbles preferred to grow in the shape bounded by{100}*** statistical analysis of the characteristic parameters of helium bubbles,the functions between the average size,number density of helium bubbles,swelling rate and irradiation damage were ***,an empirical formula for calculating the size of helium bubbles during the annealing was also provided.

关键词： helium bubbles in-situ TEM observation ion irradiation annealing molybdenum

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A revised method to simulate the dynamic characteristic of vibration isolator of main pump 27

A revised method to simulate the dynamic characteristic of v...

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27th International Congress on Sound and Vibration, ICSV 2021

作者： Zhang, Wenzheng Xiong, Furui Liu, Shuai Yuan, Zhihao Jiang, Xiaozhou Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9788378807995

It's important to choose suitable kinetic parameters for vibration isolators to simulate the dynamic characteristic. The kinetic parameters have significant influence on the vibration reduction of vibration isolators. In this paper, the kinetic parameters of two kinds of metal-rubber (MR) vibration isolators of main pump are measured to accurately acquire the dynamic characteristic. The origin impedance and cross point impedance data is tested on the testing platform. The four-terminal parameter method is applied to calculate the stiffness and damping value of the MR vibration isolators. Unfortunately, the method can't simulation the influence of the peak value behind the standing wave frequency, which is caused by the internal resonance of the vibration isolators. A revised rod vibration model is adopted to simulate the internal resonance, because the rod vibration model can express the high order peak. The numerical results are in good agreement with experimental results. The revised method can be used to simulate the dynamic characteristic of vibration isolators. © "Advances in Acoustics, Noise and Vibration - 2021" Proceedings of the 27th International Congress on Sound and Vibration, ICSV 2021. All rights reserved.

关键词： Kinetic parameters

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Testing Verification of Pressurizer Control in Nuclear Power Plant Based on Comparative Simulation 5th

Testing Verification of Pressurizer Control in Nuclear Power...

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5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020

作者： Zhang, Xu Deng, Zhi-Guang Peng, Hao Chen, Qi Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789811634550

The pressurizer is an important equipment to maintain the stability of primary circuit in nuclear power plant. Pressurizer control system needs to be verified by effective testing. The most popular testing verification method on digital control system (DCS) is the discrete script tests. However it cannot make effective tests on the continuous variable process system. In this paper, a completed testing structure aiming on DCS is designed. The structure includes four levels: discrete script test, simulation test, stimulation test and online comparison test, which are in the progressive relationship, forming the comprehensive design and test system for the DCS. The system is applied to the verification of pressurizer in nuclear power plant. The HPR 1000 MW PWR model and pressurizer control system are used to make the simulation and verification tests. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Digital control systems

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design and Implementation of Translation-Based Virtual DCS Based on Simulink 5th

Design and Implementation of Translation-Based Virtual DCS B...

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5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020

作者： Zhang, Xu Deng, Zhi-Guang Ma, Quan Liu, Ming-Ming Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789811634550

The translation-based virtual DCS based on Simulink can realize the function of virtualizing the physical DCS. This paper presents a method to virtualize physical DCS by using Simulink to realize the functions of running, freezing, acceleration and deceleration, setting and acquiring variable values, malfunction simulation, snapping and loading initial conditions, etc. Virtual DCS realizes the configuration translation by translating the configuration files of the physical DCS platform to Simulink platform, generating codes by using the configuration, and compiling the codes into algorithm files. The virtual DCS is combined with process model software to form a closed-loop, which simulates the level control system of the steam generator of a megawatt pressurized water reactor nuclear power plant for verification. Effective results have been achieved, which proves that the translation virtual DCS can meet the simulation effect of the simulator. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Simulink

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Influence of Different Factors on Fault Current Under DC Side Fault of Photovoltaic Grid Connected System 5

Influence of Different Factors on Fault Current Under DC Sid...

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5th IEEE Conference on Energy Internet and Energy System Integration, EI2 2021

作者： Luo, Yongyi Qing, Xianguo Peng, Renyong Huangfu, Yuzhao Cui, Ao Wang, Zhaosu Zhang, Zhiqiang Peng, Ziheng Liao, Chengyu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9781665434256

Modular multilevel converter (MMQ has many advantages, such as low loss, flexible control and so on, which has been widely used in photovoltaic grid connected system. However, the photovoltaic output has some instability, and the damping of the flexible DC system is also low, which puts forward a severe test for the stable operation of the power grid. Firstly, this paper describes the basic structure of the photovoltaic system connected by MMC. Secondly, the photovoltaic grid connected system model based on PSCAD illustrates the fault current characteristics under DC side fault, and simulates and analyzes the influence of different factors in the system on the fault current. © 2021 IEEE

关键词： Power converters

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Deep learning based fault diagnosis for chemical process with statistical feature fusion

Deep learning based fault diagnosis for chemical process wit...

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第42届中国控制会议

作者： Lei Zhang Hao Xia Bao Chao School of Control Science and Control Engineering Dalian University of Technology Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China

The existing fault diagnosis methods based on deep neural networks mostly rely on process data for fault classification and diagnosis,which makes it difficult to distinguish minor faults with similar data ***,this paper proposes a deep learning-based fault diagnosis model that combines statistical indicators and neural *** analyzing and calculating the relevant information entropy to screen the statistical signal features of time domain and frequency domain,we can extract more hidden information from the raw data,and use the convolutional autoencoder to compress the statistical indicators for feature extraction,and use CNN network to extract features from raw ***,the two sets of features are fused and input into the LSTM network to obtain temporal information for fault *** conducted on the Tennessee Eastman(TE)process show that the proposed model outperforms typical classifiers and improves the diagnostic accuracy of minor faults.

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Comparative study on thermal stress analysis and fatigue curve in stress and fatigue calculation of nuclear equipment 28

Comparative study on thermal stress analysis and fatigue cur...

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2021 28th International Conference on Nuclear Engineering, ICONE 2021

作者： Shao, Xuejiao Xie, Hai Yixiong, Y. Zhang, Liping Fu, Xiaolong Mi, Xue Li, Hui Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791885246

In the stress and fatigue evaluation of primary nuclear equipment, thermal stress calculation and fatigue curve have a great impact on the calculation results. There is a problem of stability in the step integral when calculating the thermal stress. The transient heat conduction changes rapidly near the initial temperature time point. It is critical to choose the right sub steps. In the nuclear code, the design fatigue curve in the air environment is given by applying a factor of 2 on stress or a factor of 20 on cycles. The factors are used to consider various influences such as data scatter, structure size, surface roughness and load. The factors of fatigue curves in ASME BPVC 2007 edition + 2009 addendum and French AFCEN's RCC-M 2017 edition RPP 2 have changed. Due to the changes of the original test data and modificative factors, the new fatigue curve and the original fatigue curve are crossed. In code case N-761 of ASME, fatigue curves considering the influence of primary coolant environment are given under different strain rates. In the calculation of thermal transient using commercial ANSYS software, the setting of time step has a great influence on the thermal stress. This paper compares and analyzes the influence of different calculation methods on the thermal stress at different positions of the model. The effect of different fatigue curves on fatigue life is also discussed considering different air design curve and different strain rate fatigue curve in water. The results show that the fatigue results obtained by using the modified ASME or RCC-M air fatigue curve are smaller than those before the change when the usage factor is large to a certain extent. After considering the environmental fatigue curve, the fatigue results increase significantly. The accuracy of thermal stress calculation can be significantly improved by adding time points and refining time steps near the time points after the transient sharply changes, otherwise the influence of thermal

关键词： Thermal stress

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Preliminary research on the thermal-mechanical coupling behavior simulation method of m3 fuel 28

Preliminary research on the thermal-mechanical coupling beha...

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2021 28th International Conference on Nuclear Engineering, ICONE 2021

作者： Changbing, Tang Yongjun, Jiao Yuanming, Li Kun, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institution of China Chengdu China

ISBN: (纸本)9780791885253

M3 fuel which microencapsulated TRISO particles in zirconium metal matrix is an integrated fuel designed to replace the traditional pellet-cladding fuel rod. The fuel design can effectively solve the problems of LWR fuel, such as water side corrosion, abrasion, pellet-cladding interaction, stress corrosion cracking and internal pressure bracing. Because of the multiple coating structure of TRISO particles and complex contacting behavior and deformation between TRISO particle and metal matrix, M3 fuel exhibits complex in-pile behavior. In order to establish the simulation method for the M3 fuel, the three-dimensional model was established by using ABAQUS software. The complex contacting behavior and deformation of coated layers and matrix for M3 fuel was considered. The results indicated that bonded strength between TRISO particle and Zr matrix has great effect on the stress distribution of SiC layer and matrix. The vulnerable area of Zr matrix located in the nearest position of TRISO particle to TRISO particle. The maximum tensile hoop stress of SiC layer was up to 150 MPa under strong bonding state, while SiC layer suffered compressive stress during all operation time for the weak bonding state. The failure probability of SiC layer was about 7 10-3 under strong bonding state which much higher than the weak ones. Thus, the integrity of SiC layer can be maintained by controlling the bonding strength between TRISO particle and Zr matrix during manufacturing process. © 2021 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Silicon carbide

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design of Emulation System for Safety DCS 5th

Design of Emulation System for Safety DCS

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5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020

作者： Peng, Hao Zhang, Xu Deng, Zhi-Guang Chen, Qi Zhang, Yu Jiang, Wei Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789811634550

DCS (Digital Control System) is a very important part in safety protection in NPP (Nuclear Power Plant). Virtual DCS realizes the algorithm configuration of physical DCS running on general computers and gets rid of the limitation of hardware. In this paper, an emulation system (virtual DCS) is designed using virtual DPU technology. The virtual DCS can be used to verify the algorithm logic with the closed-loop system, which is composed by virtual DCS and digital reactor processing model together. The virtual DCS and controlled object are closed to test the control effects and in this way to verify the design of the NPP DCS. For the purpose of scientific research, training and design verification, virtual DCS should have malfunction simulation and other functions. These functions reflect the superiority of emulation technology. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Digital control systems

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NUMERICAL ANALYSIS ON FLOW AND HEAT TRANSFER CHARACTERISTICS OF LBE IN NARROW RECTANGULAR CHANNELS 30

NUMERICAL ANALYSIS ON FLOW AND HEAT TRANSFER CHARACTERISTICS...

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30th International Conference on Nuclear Engineering, ICONE 2023

作者： Jiang, Yanming Li, Xiaochang Tian, Ruifeng Lu, Chuan Song, Zhiguang College of Nuclear Science and Technology Harbin Engineering University Harbin China Heilongjiang Provincial Key Laboratory of Nuclear Power Plant Performance and Equipment Harbin Engineering University Harbin China College of Aerospace and Civil Engineering Harbin Engineering University Harbin China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888982566

The lead-bismuth eutectic alloy (LBE) is a candidate coolant for the generation IV liquid metal reactors, and the plate-type fuel assemblies are widely used in the small or research reactors. However, the turbulent heat transfer behaviors of low Prandtl number LBE are quite different from that of ordinary fluids due to its violation in Reynolds analogy, and its flow and heat transfer process in narrow rectangular channels need to be studied with new methods. For this purpose, the authors conduct numerical simulation and analysis of turbulent flow of the LBE in narrow rectangular channel and compare the numerical simulation results with correlation proposed for liquid metal, moreover, the applicability of different near wall treatment methods, turbulence models and turbulent Prandtl number (Prt) models is compared. The focus of the analysis is on the impacts of the collocation of various models on the Nusselt number, the flow redistribution phenomena, as well as the difference in flow and heat transfer capacity in channels. According to the results, the suggested turbulence model and Prt model for different Peclet (Pe) numbers are recommended, besides the flow redistribution phenomenon in the three channels fuel assembly can be ignored, only slightly affects the flow and heat transfer in the narrow rectangular inlet region. © 2023 by JSME.

关键词： Turbulence models

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