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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

作者： Cai, Rong Yue, Nina Fang, Hongyu Chen, Baowen Liu, Lili Ma, Zehua Science and Technology on Reactor System Design Technology Laboratory Chengdu China Cnnc Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology Chengdu China Xi'an Jiaotong University Xi'an Shaanxi China

ISBN: (纸本)9780791883785

The marine nuclear power plant operating in the marine environment has complicated motion under the influence of wind and waves. The movement of marine nuclear power plant will affect the thermal-hydraulic characteristics of its nuclear reactor system. Compared with other typical motion conditions, the effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system are the most complex. In order to study the effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system, a thermal-hydraulic system code for motion conditions named STAC was developed. The STAC code was verified by the experiments conducted in Japan. The effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system under forced circulation and natural circulation are studied with the STAC code. The simulation results show that the thermal parameters of the reactor system under rolling condition fluctuate periodically. The fluctuation period of the thermal parameters of the core is half of the rolling period, and the fluctuation periods of other thermal parameters are the same as the rolling period. The effect of rolling condition on thermalhydraulic parameters under forced circulation is smaller than that under natural circulation. The fluctuation amplitudes of the thermal parameters increase with the angle amplitude of the rolling condition. There is a rolling period with the smallest fluctuation amplitude. Under the rolling condition with short period, the fluctuation amplitudes of the thermal parameters increase and their average values change rapidly as the rolling period decreases. Under the rolling condition with large period, the fluctuation amplitudes of the thermal parameters increase with the rolling period, and they tend to fixed values. © 2020 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Nuclear fuels

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Dual-Target Point Cloud Registration for Partially Visible Data Using Local and Global Features

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SSRN 2024年

作者： Rao, Zhifeng Chen, Yuang Cao, Ming Lin, Zhiyun School of System Design and Intelligent Manufacturing Southern University of Science and Technology Shenzhen518055 China Shenzhen Key Laboratory of Control Theory and Intelligent Systems Southern University of Science and Technology Shenzhen518055 China University of Groningen Netherlands Peng Cheng Laboratory Shenzhen518055 China

Point cloud registration is a challenging task when only partially visible data is available. Recently, many learning-based methods have been proposed for this problem and have achieved satisfactory performance. However, they use only one source point cloud and fail to pay attention to the key factor of registration: alignment of attitudes. Based on this phenomenon, we propose a dualtarget point cloud registration model: An end-to-end model, which uses multiple source point clouds and for each source point cloud, a new created target point cloud is added to pay more attention to the alignment of attitudes. Our model is divided into two components: coarse and fine registrations. First, an initialization module is introduced for coarse registration, in which multiple source point clouds are used and for each source point cloud, a new target point cloud specifically for aligning the attitudes is added. Second, we design a two-step Attention-based Representative Overlapping-Point Selection module to select representative overlapping points for fine registration, which uses both global and local features of the point clouds. In the first step, overlapping scores are predicted using global features. In the second step, a feature-matching matrix is obtained based on local features. Representative overlapping points are selected based on the overlapping scores and the feature-matching matrix. Using these points, a weighted SVD algorithm is used to estimate the transformation of fine registration. Extensive experiments on ModelNet40, 7Scenes and ICL-NUIM show that our method achieves the state-of-the-art compared to other learning-based methods. © 2024, The Authors. All rights reserved.

关键词： Matrix algebra

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Natural antibacterial membranes prepared using Schisandra chinensis extracts and polyvinyl alcohol in an environment-friendly manner

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Chemosphere 2024年 346卷 140524页

作者： Jia, Wenting Jiang, Shanxue Wang, Fang Li, Jing Wang, Zeru Yao, Zhiliang School of Ecology and Environment Beijing Technology and Business University Beijing100048 China State Environmental Protection Key Laboratory of Food Chain Pollution Control Beijing Technology and Business University Beijing100048 China School of System Design and Intelligent Manufacturing Southern University of Science and Technology Shenzhen518055 China

Foodborne pathogens can cause food spoilage and lead to food safety issues. In recent years, food packaging has received a lot of attention. Traditional packaging membranes are non-biodegradable and remain in the environment for a long time. In this study, natural antimicrobial substances were extracted from Schisandra chinensis by a green extraction process using distilled water as the solvent, and the effects of different treatment on the antimicrobial activity of the extract were compared. At the same time, four types of Schisandra chinensis antimicrobial membranes were prepared using polyvinyl alcohol (PVA) as the substrate. The whole extraction and membrane preparation process did not involve organic solvents, making the process green and environment friendly. Material characterization included inverted biological microscopy, scanning electron microscopy (SEM), atomic force microscopy (AFM), Fourier transform infrared spectroscopy (FTIR), tensile strength test, pore size measurement, water uptake test, etc. Among them, no extract particles were observed with the naked eye on the surfaces of MⅡ and MⅣ. MⅡ has a uniformly transparent, nearly colorless morphology and is the most tensile. MⅣ surface is flat and smooth, the microstructure is dense and uniform. At the same time, the four types of membranes were tested against common pathogenic bacteria for 12 h, and the OD600 trend revealed the excellent antimicrobial activity of the membranes against S. aureus, MRSA, E. coli, and L. monocytogenes. The membranes could also be reused at least once. This study provides a new idea for preparing natural plant-based antimicrobial membranes. © 2023 Elsevier Ltd

关键词： Food safety

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Towards Scalable and Privacy-Preserving Data Sharing in Internet of Digital Twins

Towards Scalable and Privacy-Preserving Data Sharing in Inte...

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IEEE Conference on Global Communications (GLOBECOM)

作者： Xiangyu Shi Guanjie Li Tom H. Luan Zhou Su Shui Yu Wen Wu School of Cyber Engineering Xidian University Xi’an China Information System Technology and Design Pillar Singapore University of Technology and Design Singapore School of Cyber Science and Engineering Xi’an Jiaotong University Xi’an China School of Computer Science University of Technology Sydney Sydney Australia Frontier Research Center Peng Cheng Laboratory Shenzhen China

ISBN: (数字)9798350351255

ISBN: (纸本)9798350351262

A Digital Twin (DT) is a software agent of a physical entity in virtual space, transcending the limitations imposed by physical constraints to enable intelligent services. The emergence of the Internet of Digital Twins (IoDT), by connecting DTs as a network, provides a reliable solution for streamlining the sharing of extensive real-time data among DTs. However, ensuring the security and efficiency of highly sensitive DT data remains a significant challenge in the distributed and dynamic IoDT storage environment. In this paper, we propose a comprehensive scheme that integrates blockchain, Distributed Hash Table (DHT), and Attribute-Based Encryption (ABE) to establish an IoDT data-sharing system. First, we introduce an ABE scheme to achieve data confidentiality and fine-grained access control. By implementing a key generation protocol, we address key escrow concerns in ABE. Second, to ensure bidirectional data confidentiality in data sharing without revealing the identities of DTs, the DHT, and blockchain are jointly applied to achieve resource registration and discovery. Through an XOR mapping operation mechanism, DT data are distributed across different DHT network nodes, reducing DT nodes’ storage consumption and effectively addressing the scalability issue of IoDT storage. Finally, we provide performance evaluations to demonstrate the reliability and efficiency of our proposed scheme. Our scheme strikes a balance between efficiency and security, exhibiting efficient performance in IoDT data sharing compared to other ABE and blockchain schemes.

关键词： Access control Data privacy Scalability Software agents Real-time systems Blockchains Digital twins Internet Encryption Software reliability

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The Calculation Method of Neutron Transport Equation and its Conjugate Equation Based on Finite Deconvolution Neural Network

SSRN

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SSRN 2022年

作者： Li, Xiangyu Cheng, Kun Huang, Tao Tan, Sichao Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment Harbin Engineering University Harbin15001 China College of Nuclear Science and Technology Harbin Engineering University Harbin150001 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

Aiming at the problem that the current neutron transport equation solving method, which is mainly numerical calculation, takes too long to calculate the inverse of the stiffness matrix, this paper designs a shallow neural network algorithm based on finite deconvolution neural network, which does not need to calculate the inverse matrix for the sti ness matrix or use other iterative algorithms. The algorithm uses a deconvolution neural network algorithm as the basic structure, replaces the deconvolution kernel with the finite volume method, and uses the calculation equation of reactor power as the loss function. The gradient descent method and the power residual are used to update the algorithm parameters to ensure algorithm convergence. The algorithm can use the neutron transport equation and its conjugate equation to calculate the distribution of neutron flux density and neutron importance in the space. © 2022, The Authors. All rights reserved.

关键词： Numerical methods

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Numerical study of fuel melting and molten migration based on the mps method

Numerical study of fuel melting and molten migration based o...

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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

作者： Lei, Zhong Deng, Jian Li, Wei Wu, Xiaoli Deng, Chunrui Nuclear Power Institute of China Chengdu Sichuan China Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China

ISBN: (纸本)9780791883785

Core melting and molten migration behavior are hot and difficult issues in the field of nuclear reactor severe accident research. The Moving Particle Semi-implicit (MPS) meshless method has potential to simulate free-surface and multiphase flows. In this study, the MPS method was utilized to simulate the melting process of UO2-Zr rod-type fuel elements. The models of heat conduction with phase change, simplified UO2-Zr eutectic reaction, viscous flow and surface tension were implemented with the framework of standard MPS method. Then, the improved MPS code was used to simulate and analyze the process of high-temperature melting and characteristics of molten migration and solidification in the coolant channel, aiming at revealing the severe accidents for light water reactors (LWR), particularly the early core damage. The results showed that compared with the case of higher initial temperature, when the initial temperature of molten UO2 is lower, more molten UO2 will solidify on the surface of rod cluster, and the blockage of upper flow channel caused by molten UO2 is more serious. In addition, this study also demonstrated the potential of the MPS method for the study of complicated severe accident phenomena in not only traditional LWR but also advanced nuclear reactors in the future. © 2020 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Solidification

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Study on the liquid seal discharge process in an over-pressurized accident

Study on the liquid seal discharge process in an over-pressu...

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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

作者： Wu, Dan Deng, Jian Du, Sijia Qian, Libo Nuclear Power Institute of China Chengdu Sichuan China Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China

ISBN: (纸本)9780791883785

In an over pressure accident, one or more pressurizer safety(or relief) valves will open due to the rapid pressure rise process. Once the safety(or relief) valves are open, the liquid seal will be discharged, and this will generate great discharge force to the downstream pipes. Multi-level protection is chosen using pressurizer safety(or relief) valves with different setpoint in most of Nuclear Power Plant, especially in the self-designed Generation-III Nuclear Power Plants. As the over pressure accident progresses, one or more safety(or relief) valves will be open. The downstream pipes will experience one or more times of impacts, which will influence the arrangement of the pipes. The whole discharge process is very complex, and the key influence factors are the pressure rise rate, safety(or relief) valve opening time, liquid seal temperature and volume, and the arrangement of the downstream discharge pipes. In present paper, liquid seal discharge process in an over pressure accident is studied. The pressure rise rate is so fast that three safety(or relief) valves will open one after another, which will generate three impacts on the downstream discharge pipes. It is found that for a specific design of Nuclear Power Plant, well design of the safety(or relief) valve setpoint is very important to the discharge force analysis results. © 2020 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Liquids

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Propagation Characteristics of End-Winding Insulation Fatigue Damage in Variable Frequency Motor Under Multi-Field Coupling

Propagation Characteristics of End-Winding Insulation Fatigu...

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IEEE Conference on Electromagnetic Field Computation

作者： Bangwei Zhang Haijun Zhang Jiashun Wang Yuxin Cao Hubei Key Laboratory of Power System Design and Test for Electrical Vehicle Hubei university of Arts and Science Xiangyang China School of Electronic Information Engineering Taiyuan University of Science and Technology Taiyuan China

ISBN: (数字)9798350348958

ISBN: (纸本)9798350348965

In this paper, the fatigue propagation mechanism of motor stator insulation damage under variable frequency drive is studied by combining theoretical analysis and finite element numerical simulation. Based on the magneto-thermo-solid coupling and fatigue damage theory, the stress-strain state, crack damage degree and propagation rate of motor stator insulation are analyzed. The crack damage propagation at different positions of the end winding outlet, middle and nose end is simulated and calculated by three-dimensional finite element method. It is found that the stress, strain and stress intensity factor of the end winding insulation at the outlet position change violently, which reflects that the crack damage is easier to expand and the propagation rate is greater. The results of this paper can provide reference for the evolution law, fault diagnosis and optimization design of insulation damage of variable frequency drive motor under complex working conditions.

关键词： Couplings Insulation Windings Stator windings Variable speed drives Motors Fatigue

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KYLIN-V2.0 code calculation ability verification based on VERA benchmark

KYLIN-V2.0 code calculation ability verification based on VE...

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2020 International Conference on Physics of reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020

作者： Wang, Dongyong Yu, Yingrui Peng, Xingjie Wang, Chenlin Liu, Kun Chai, Xiaoming Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9781713827245

Virtual Environmental for reactor Analysis (VERA) benchmark was released by the Consortium for Advanced Simulation of Light water reactors (CASL) project in 2012. VERA benchmark includes more than ten problems at different levels, from 2D fuel pin case to 2D fuel assembly case to 3D core refuelling case, in addition, reference results and experimental measured data of some problems were provided by CASL. Fuel assemblies in VERA benchmark are various, including control rod assemblies, Pyrex assembly, IFBA assembly, WABA assembly and gadolinium poison assembly, and so on. In this paper, various fuel assembly models in the VERA benchmark have been built by using KYIIN-V2.0 code to verify its calculation ability from 2D fuel pin case to 2D fuel assembly case to 2D 3x3 fuel assembly case, and making a comparative analysis on the reference results in VERA benchmark, as well as the calculation results of the Monte Carlo code RMC. KYLIN-V2.0 is an advanced neutron transport lattice code developed by Nuclear Power Institute of China (NPIC). The subgroup resonance calculation method is used in KYIIN-V2.0 to obtain effective resonance self-shielding cross section, method of modular characteristics (MOC) is adopted to solve the neutron transport equation, and CRAM method and PPC method is adopted to solve the depletion equation. The numerical results show that KYLIN-V2.0 code has the reliable capability of direct heterogeneous calculation of 2D fuel assembly, and the effective multiplication factor, assembly power distribution, rod power distribution and control rod reactivity worths of various fuel assemblies that are calculated by KYLIN-V2.0 are in better agreement with the reference. © The Authors, published by EDP sciences. This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://***/licenses/by/4.0/).

关键词： Control rods

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Research on analysis and modeling methods for lbloca in nuclear power plants based on autonomous loca analysis platform arsac

Research on analysis and modeling methods for lbloca in nucl...

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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

作者： Zhou, Jiayue Wu, Dan Ding, Shuhua Jiang, Guangming Nuclear Power Institute of China Chengdu Sichuan China Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China

ISBN: (纸本)9780791883785

In order to meet the demand of continuous innovation of technologies and the general trend of autonomous nuclear power plants design and export of nuclear power plants, it is necessary to develop an autonomous LOCA analysis platform and corresponding analysis methods for the most complex design basis accidents. In this paper, the characteristics of LOCA analysis platform ARSAC, designed by Nuclear Power Institute of China, and the code ARSAC-K which meets the requirements of the US Federal Code 10 CFR 50.46 Appendix K model are introduced as well as a set of LOCA analysis methods and modeling methods. Based on the international advanced LOCA analysis code development concept, the code ARSAC has made new breakthroughs in matrix algorithms, key thermal hydraulic models and so on. Validation work has also been carried out in-depth. A set of advanced LOCA analysis methods has been developed using code ARSAC-K and advanced power plant parameter sampling methods. Analysis on LBLOCA of nuclear power plants with code ARSAC-K was performed, and the impact of different modeling methods on the LOCA analysis results was studied. To ensure the rationality and conservativeness of the analysis results, a set of reasonable and conservative modeling methods is fixed on the basis of a large number of sensitivity analyses for subsequent analysis and calculation. In the future, a lot of optimization work will be done to improve the LOCA code and corresponding methods. © 2020 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Nuclear power plants

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