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检索条件"机构=Science and Technology on Reactor System Design"

共 626 条记录，以下是321-330 订阅

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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...

引用

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...

引用

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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Numerical Simulation of Flow Boiling Heat Transfer in Helical Tubes Under Marine Conditions 23rd

Numerical Simulation of Flow Boiling Heat Transfer in Helica...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Yuan, Leqi Cheng, Kun Bian, Haozhi Liao, Yaping Jiang, Chenxi Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Heilongjiang Harbin China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789819910229

Lead-based cooled reactors in most countries and some small reactors at sea use helical tube steam generators. Compared with U-tubes, the convection heat transfer coefficient in the spiral tube is higher, the structure is more compact, and the secondary flow is generated under the action of centrifugal force and gravity, which can achieve the effect of wetting the inner wall of the tube. However, due to the importance of the steam generator in the reactor and the complexity of the flow and boiling in the helical tube, the aggregation behavior of bubbles, the distribution of the two-phase interface and the secondary flow in the tube will significantly affect the heat transfer characteristics, so the gas-liquid phase in the tube is studied. Distribution, changes in heat transfer coefficients, and fluid flow characteristics are very important. In order to study the boiling heat transfer characteristics of helical once-through steam generators under static and marine conditions to provide safe and reliable energy supply for offshore facilities such as marine floating, this study uses STAR-CCM+ software, VOF method and Rohsenow boiling model to study the heat transfer capacity and flow characteristics of flow boiling in a helical tube under swaying and tilting conditions. The gas-liquid phase distribution characteristics, secondary flow variation characteristics and convective heat transfer coefficient of the fluid under different swing functions and inclined positions are obtained by numerical calculation, and the law of physical parameters changing with the cycle is found. The research results show that the secondary flow and heat transfer capacity in the tube change with the cycle, and the change is most obvious at the tube length of 0.8m. 5% of the normal condition;when the inclination angle is 45°, the maximum increase of the convection heat transfer coefficient is 16.8%, and the maximum decrease is 6.6%. © 2023, The Author(s).

关键词： Computational fluid dynamics

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Demo Abstract: Observability-driven sensor deployment in smart academic environments 14

Demo Abstract: Observability-driven sensor deployment in sma...

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14th ACM Conference on Embedded Networked Sensor systems, SenSys 2016

作者： Agarwal, A. Jaiswal, K. Gudhaka, U. Munigala, V. Ramamritham, Krithi Karmakar, Gopinath Department of Computer Science Engineering Indian Institute of Technology Bombay United States Reactor Control System Design Section Bhabha Atomic Research Centre India

ISBN: (纸本)9781450342636

Saving energy without causing discomfort and without de-manding human intervention is the need of the day. It is important to develop sensor systems which not only satisfy user requirements, but also take energy consumption into consideration. In this demo, we present the sensing subsys-tems of a Smart Academic Environment, based upon the core concept of Observability' [1] which-while satisfying user needs-helps to reduce the number of sensors required. © 2016 Copyright held by the owner/author(s).

关键词： Observability

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A Novel Model for Dynamic Process Study of reactor Control Rod Drive Mechanism 26

A Novel Model for Dynamic Process Study of Reactor Control R...

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

作者： Yang, Yun Xu, Qiwei Zhang, Xuefeng Yu, Tianda Chen, Xinan Zhao, Yizhou Chongqing University National 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)9798350317589

The magnetic jack type control rod drive mechanism (CRDM) is a critical electromagnetic actuator utilized in reactors, with its movable components subject to the combined effects of electromagnetic force, liquid resistance, spring force, and other factors, resulting in highly nonlinear and uncertain motion characteristics. This article establishes a novel model for the dynamic process analysis of the CRDM. The dynamic electromagnetic force and inductance of the CRDM are analyzed based on the equivalent magnetic network (EMN) model, taking into account mesh reconstruction and magnetic saturation. Through kinematic analysis and parameter coupling analysis, electromagnetic and kinematic parameters during the CRDM lifting process are obtained. Finally, finite element analysis (FEA) and experimentation are conducted to validate the accuracy of the proposed model. © 2023 IEEE.

关键词： Kinematics

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Performance comparison of different approximation schemes in matrix MOC

Performance comparison of different approximation schemes in...

引用

2018 International Conference on Physics of reactors: reactor Physics Paving the Way Towards More Efficient systems, PHYSOR 2018

作者： Yong, Zheng Peng, Minjun Zhou, Yueshan Qiang, Shenglong Ping, An Wei, Lu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Harbin150001 China

ISBN: (纸本)9781713808510

The method of characteristics (MOC) with matrix form has theoretically more favorable features than its standard application, since the time-consuming track sweeping operations are replaced with explicit solution of matrix equation. In traditional MOC, there are three optional discretization strategies: the step characteristic method, diamond difference scheme and linear source approximation. However, their performances in matrix MOC have not be reported so far. The current paper develops their matrix forms and solves the resulted linear systems using preconditioned generalized minimal residual (PGM-RES) method. Additionally, their performances with respect of computation accuracy and efficiency are compared with each other, by simulating a homogeneous hexagonal cell problem and the 2D C5G7 benchmark. The results show that their performances in matrix form are different from that of traditional form. With the same angular quadrature and region partition scheme, the step characteristic method is more efficient significantly than the diamond difference scheme and linear source approximation. Whether the diamond difference scheme and linear source approximation can improve the calculation accuracy or not depends on whether the the spatial mesh is fine enough for every scheme. For the coarser spatial partition strategy, diamond difference scheme and linear source approximation can significantly improve the accuracy of local pin power. © 2018 International Conference on Physics of reactors, PHYSOR 2018: reactor Physics Paving the Way Towards More Efficient systems. All rights reserved.

关键词： Diamonds

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Experimental Study on Aerosol Removal Effected by Spray Characterization 23rd

Experimental Study on Aerosol Removal Effected by Spray Char...

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23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Hu, Peizheng Xu, Zhen Wang, Junlong Tong, Lili Cao, Xuewu School of Mechanical Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789811988981

The containment spray system is widely used in pressurized water reactor nuclear power plants, which can not only remove the heat in the containment but also remove the fission products suspended in the containment to reduce the discharge of radioactive substances to the environment during accident conditions. The aerosol removal behavior is affected by the spray droplet size distribution. The effect of different spray flow rates on aerosol removal is studied experimentally, and an improved evaluation model is established based on the spray droplet size distribution to analyze the efficiency of removal mechanisms. The experiments are carried out in the CATH (Containment Aerosol Thermal-Hydraulics) test facility with a total volume of 18.5 m3, where aerosols are injected and scrubbed by spray droplets. The spray droplets are generated by a full-cone spray nozzle at the volume flow rate of 0.4 m3/h and 0.6 m3/h, where droplet size distribution is measured by a Laser Diffractometer. Polydisperse particles of TiO2 are used to simulate the solid aerosol, whose diameters are in the range of 0.2 ~ 1.6 μm measured with an Aerosol Spectrometer. Experimental results show that the removal efficiency is higher for the larger particles, and the global removal efficiency of aerosols improved with the increase of spray flow rate from 0.4 to 0.6 m3/h. In addition, the removal efficiency of inertial impaction, interception, Brownian diffusion are quantitatively evaluated by the improved model, which shows that the effect of inertial impaction and interception is more significant for large particles. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Aerosols

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Evaluation methods of fatigue in nuclear power design

Evaluation methods of fatigue in nuclear power design

引用

2019 Transactions of the American Nuclear Society, ANS 2019

作者： Wang, Donghui Zeng, Qingna Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 328# 1st section Chuangshun Dadao Avenue Chengdu610213 China

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A computer code for thermal-hydraulic analysis of steam generator with axial preheater/economizer

A computer code for thermal-hydraulic analysis of steam gene...

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AISTech 2018 Iron and Steel technology Conference and Exposition

作者： Wu, Ge He, Gening Wang, Haisong Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory NO.328 First Sec. of Changshun Ave. Shuangliu District Chengdu China

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The application of Lagrangian particle Tracking method in the study of steam generator sludge collector

The application of Lagrangian particle Tracking method in th...

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2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017

作者： Wu, Ge Cheng, Xiang Huang, Wei Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory NO.328 First Sec. of Changshun Ave. Shuangliu District Chengdu China

ISBN: (纸本)9784890471676

During the operation of the Pressurized Water reactor recirculation steam generator, sludge particles from the feed water system and secondary system, mainly corrosion products, converge in the secondary side of steam generator. Since the saturated steam exiting the steam generator carries almost no sludge, the corrosion products' concentration increases with time. Although a part of the sludge can be removed by the blowdown system, the rest will either suspend in the water or deposit as a result of gravity, boiling or turbulence. Some sludge particles deposited on the surfaces of heat transfer tubes, tube sheet, and tube supporting plates or in the gaps around will cause a variety of problems, such as accelerating component device corrosion. The sludge collector is a passive device located in the upper internals of a PWR U-tube natural recirculation steam generator. It is able to trap and collect the sludge particles suspending in the secondary side fluid, which helps in reducing the amount of sludge available to settle on the tube bundle area. In this paper, the flow conditions and the sludge particle tracks around the sludge collector in a typical U-tube recirculation steam generator are studied by using a Computational Fluid Dynamics method. For the simulation method, a k-e model is selected as the turbulent model, and the two-way coupling Lagrangian Particle Tracking scheme is employed to account for the momentum transfer effects between the continuous phase of fluid and the discrete phase of particles. The forces acting on the sludge particles in this paper include the drag force, buoyancy force, and other additional forces such as added mass force and pressure gradient force. And the number of the representative particles captured by the sludge collector is also studied, while the mass flow rate entering the sludge collector is always paid more attention. The simulation results have successfully captured the flow patterns and the tracks of the representative

关键词： Steam generators

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