检索结果-内蒙古大学图书馆

Chinese Automation Congress (CAC)

作者： Weihang Lv Na Qin Xinyu Zhao Peng Yuan Jie Huang School of Electrical Engineering Southwest Jiaotong University Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (数字)9781728176871

ISBN: (纸本)9781728176888

To solve the complex 3-D space pipe routing problem, an algorithm framework combining genetic algorithm and adaptive A * algorithm (AAGA) is proposed. The initial population of the genetic algorithm is generated using the adaptive A * algorithm combined with the concept of intermediate join points, this method is also used in the generation of sub-paths in the crossover and mutation operations of genetic algorithms. On the one hand, this method improves the quality of the initial population and speeds up the optimization of genetic algorithm, on the other hand, it solves the problem that the genetic algorithm combined with the traditional A * algorithm (AGA) is prone to redundant inflection points. Finally, on the premise of ensuring pipeline connectivity, pipeline length and number of inflection points, the constraints of pipeline center of gravity and minimum bending radius are added to carry out simulation experiments. Simulation results show that the AAGA has better performance than adaptive A * algorithm and AGA.

关键词： Pipelines Genetic algorithms Layout Statistics Sociology Biological cells Routing

来源：评论

学校读者我要写书评

暂无评论

Hydrogen risk analysis of a large pressurized water reactor using hydragon code 27

Hydrogen risk analysis of a large pressurized water reactor ...

引用

27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Zhang, Xiaolong Yu, Jiyang Huang, Tao Jiang, Guangming Zou, Zhiqiang Department of Engineering Physics Tsinghua University Beijing100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888983051

This paper presents the hydrogen risk analysis of a large Pressurized Water reactor (PWR) undergoing a severe accident using the HYDRAGON code. The code has been developed by the Department of Engineering Physics, Tsinghua University, as a hydrogen risk analysis software specialized for containment building of nuclear reactor power plants. The chemical interaction between zirconium cladding of the fuel rods and overheated coolant may release hydrogen when severe accidents occur in PWRs. The hydrogen mixed with air existing in containment may jeopardize the integrity of containment building if the flammable mixture explodes. In order to mitigate the hydrogen risk, many nuclear power plants install the Passive Autocatalytic Recombiners (PARs) that allow hydrogen and oxygen react chemically at low temperature without any sights of flame. Recombiners remove hydrogen and thereby prevent explosions. This work simulated the gas diffusion behaviors during the accident in the containment of a large PWR. The simulations obtained spatial concentration distribution of various gas species including hydrogen, oxygen, steam and nitrogen and several key parameters that are required to complete hydrogen burning and explosion investigation. Sensitivity analyses of recombiners' quantity and positions and hydrogen discharge intensity provides the reference for hydrogen mitigation measure design in the containment. The results demonstrate that the number of recombiners rather than positions has stronger influences on hydrogen mitigation. Since the installation position reflects less sensitivity, the recombiners could be arranged as higher as possible if necessary. Copyright © 2018-2019 by JSME

关键词： Hydrogen

来源：评论

学校读者我要写书评

暂无评论

Analysis and verification of burnup algorithm in reactor 27

Analysis and verification of burnup algorithm in reactor

引用

27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Hu, Yuying Luo, Qi Yao, Dong Yu, Yingrui Liao, Hongkuan Zhou, Bingyan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

Burnup algorithm analysis is an important part of the physical calculation in reactor. The computing accuracy of burnup algorithms is directly related to the correctness of the whole physical calculation. Due to the difference from the rates and lives of varieties of nuclides, burnup matrices are always sparse rigid exponential ones. At present, methods to solve exponential matrices are divided into two types, numerical methods and analytical methods. Besides, numerical methods conclude series methods, ordinary differential equation methods, polynomial methods, matrix decomposition methods and so on. In this study, some common methods to solve burnup matrices are introduced, such as Chebyshev Rational Approximation Method(CRAM), Krylov Subspace Method, Pade Approximation Method and Transmutation Trajectory Analysis(TTA). Analysis and verification for microscopic point-depletion calculation are carried out with two typical burnup chains. One of the burnup chains for verification is a decay chain of neptunium-237(237Np), which contains 13 nuclides. The other chain is an actinide nuclide reaction chain, including 25 nuclides from decay and neutron capture and 9 nuclides from fission. Because there is no close annual chain in the burnup chains used in verification, the results of using Transmutation Trajectory Analysis were thought to be accurate, and it has been used as the benchmark for comparative analysis of other methods. The final result shows, Chebyshev Rational Approximation Method has advantages in calculation accuracy and simplicity, and it is suitable to be used in large burnup calculations. Copyright © 2018-2019 by JSME

关键词： Isotopes

来源：评论

学校读者我要写书评

暂无评论

Activation of Topological Defects Induces a Brittle-to-Ductile Transition in EpithelialMonolayers

Activation of Topological Defects Induces a Brittle-to-Ducti...

引用

第十九次中国暨国际生物物理大会

作者： Yixia Chen Qigan Gao Jingchen Li Fangtao Mao Ruowen Tang Hongyuan Jiang Hefei National Laboratory for physical Science at the Microscale CAS Key Laboratory of Mechanical Behavior and Design of MaterialsCAS Center for Excellence in Complex System MechanicsDepartment of Modern MechanicsUniversity of Science and Technology of China

Epithelial monolayer is subjected to various mechanical forces,such as stretching,shearing and ***,its mechanical response to external loadings is essential for its biological ***,the mechanism of the fracture failure of epithelial monolayer remains poorly ***,by introducing a new type of topological transition,i.e.,detach transition or T4 transition,we developed a modifiedcellular vertex model to investigate the rupture of cell monolayer.

关键词： Activation of Topological Defects Induces a Brittle-to-Ductile Transition in EpithelialMonolayers

来源：评论

学校读者我要写书评

暂无评论

Assessment of Coupled Effect of Steam Pipes on Seismic Analysis of reactor Coolant system

引用

IOP Conference Series: Earth and Environmental science 2021年第4期719卷

作者： Lijuan Li Zhenyu Liu Hui Li Xianhui Ye Honglei Ai National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu Sichuan China

reactor coolant system is connected with auxiliary pipes, surge pipes and steam pipes. In order to facilitate the dynamic analysis of reactor coolant system, it is necessary to decouple the pipes connected with the reactor coolant system. Although some international standards stipulating requirements for the decoupling of subsystems from the main system, in order to further explore the influence of decoupling steam pipes, the seismic response of reactor coolant system with or without steam pipes is simulated by using ANSYS program. Firstly, the modal analysis of reactor coolant system is carried out to analysis the influence of steam pipes on the resonant frequency of reactor system. Then, the standardized seismic dynamic analysis of reactor system with or without steam pipes is carried out. The nozzle load (inlet and outlet nozzle load of main device, such as reactor pressure vessel, steam generator, pump) and support load (of main device such as reactor pressure vessel, steam generator, pump) are output and compared. According to nozzle load and support load, it can be seen that the steam pipes have little influence on the seismic analysis of reactor coolant system, i.e. steam pipes can be decoupled in the seismic analysis of reactor coolant system.

关键词：

来源：评论

学校读者我要写书评

暂无评论

Tissue-like Mechanical Confinement Inhibits Multipolar CellDivision

Tissue-like Mechanical Confinement Inhibits Multipolar CellD...

引用

第十九次中国暨国际生物物理大会

作者： Longcan Cheng Jingchen Li Houbo Sun Hongyuan Jiang Hefei National Laboratory for physical Science at the Microscale CAS Key Laboratory of Mechanical Behavior and Design of MaterialsCAS Center for Excellence in Complex System MechanicsDepartment of Modern MechanicsUniversity of Science and Technology of China

Multipolar spindle is a common feature of many cancer cells,and recent experiments have shown that it is sensitive to mechanical constraints from extracellular microenvironment,which can either suppress or promote the appearance of multipolar ***,little is known about what is the difference between various forms of mechanical confinements,and how they affect multipolarity and chromosomesegregation fidelity.

关键词： Tissue-like Mechanical Confinement Inhibits Multipolar CellDivision

来源：评论

学校读者我要写书评

暂无评论

Vibration Characteristics Analysis Of A Double-Suction Centrifugal Pump Identified By Intelligent Algorithms 12

Vibration Characteristics Analysis Of A Double-Suction Centr...

引用

12th IEEE Global Reliability and Prognostics and Health Management, PHM-Nanjing 2021

作者： Gu, Zhenyue Zhang, Mian Li, Decai Kang, Tianbo Tang, Xiuyang Wang, Zhiyuan Pei, Zhenlong Wang, Yiqiao Tianjin Key Laboratory For Advanced Mechatronic System Design And Intelligent Control School Of Mechanical Engineering Tianjin University Of Technology Tianjin300384 China China Tianjin Todelon Scicnce &TECHOLOGY CO. Ltd Tianjin China State Key Lab Of Water Resources And Hydropower Engineering Science Wuhan University Wuhan China

ISBN: (纸本)9781665401302

Due to the merits of high flow rate and high lift, double-suction centrifugal pumps are widely used for agricultural irrigation along the Yellow River in northern China. The operational conditions of the pump are highly related to the silt concentration and flow rates. Therefore, it is crucial to identify the vibration characteristics corresponding to different silt concentrations and flow rates to provide a prior guideline for pump condition monitoring. To this end, this paper explores the identification capabilities of typical intelligent models, including convolutional neural network (CNN), deep neural network (DNN), and support vector machine (SVM), to intelligently establish the connection between vibration characteristics and different flow rates and silt concentrations. Experimental studies on a double-section pump covering a range of flow rates and different silt concentrations are conducted. The results show that CNN features higher identification accuracy than DNN and SVM. © 2021 IEEE.

关键词： Vibration analysis

来源：评论

学校读者我要写书评

暂无评论

Research on cyber security countermeasure technique of safety DCS in nuclear power plant 27

Research on cyber security countermeasure technique of safet...

引用

27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Liu, Mingxing Yan, Hao Ma, Quan Liu, Guanrong Zhao, Feifei National Key Laboratory for Reactor System Design Technology Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

Cyber security event is one of the main concerns in instrumentation and control system of nuclear power plant, since the application and popularity of digital technology in industrial control area. To ensure the cyber security of safety DCS control system of nuclear power plant, this paper analyzes the security risks and vulnerabilities of field control systems, and proposes the cyber security plan for safety DCS platform. Combining with the point-to-point data flow model and the R&D of safety DCS platform, we depict the application of cyber security strategy in the product design stage. © 2018-2019 by JSME

关键词： Nuclear fuels

来源：评论

学校读者我要写书评

暂无评论

High-accuracy time synchronization method in highly reliable fiber-channel communication system 27

High-accuracy time synchronization method in highly reliable...

引用

27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Chen, Qi Jiang, Wei Tu, Xiaodong Yu, Bo Liu, Mingxing Zhang, Xu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China School of Information and Communication Engineering University of Electronic Science and Technology of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

Accompanied with strict requirements on accuracy and determinacy in nuclear power industrial safety Digital Control system (DCS), time-triggered technology has been used in Ethernet widely, while another network protocol, Fiber-Channel (FC) protocol which is popular in avionic electronic systems with hyper reliability in port to port communication stands still, even though the optical fiber cable is quite adopted by other protocols like Ethernet. One important reason is the lack of the capability to handling time sensitive tasks in FC protocol itself. In order to bring Fiber-Channel protocol into real-time applications, like safety DCS for nuclear industry, with the situation that there are pretty few researches on the time synchronization in FC protocol, this paper makes fundamental research on the solution to achieve high-accuracy time synchronization in FC protocol networks, which has been proved a vital important step to realize real time communication according to Time-Triggered Ethernet (TTE)(H. Kopetz al, 2005). By analyzing current Fiber-Channel network time communication strategies and demo-boards testing, this paper designs a method to achieve the same level or better synchronization accuracy in FC network with that in TTE, which figures out a new direction in this blank field of time synchronization in FC protocol. Furthermore, this method only asks for few resources and slight modifications on current communications for future development and improvement. Copyright © 2018-2019 by JSME

关键词： Accident prevention

来源：评论

学校读者我要写书评

暂无评论

Research about the influence of passive residual heat removal system on SGTR accident 27

Research about the influence of passive residual heat remova...

引用

27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Wu, Yirui Shan, Jianqiang Xu, Tao Ma, Haifu Yang, Junyun Yu, Hong Wang, Junlong School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi Province China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan Province China

ISBN: (纸本)9784888983051

Since the passive safety system turns out to be a desirable method to achieve simplification and increase the reliability of the performance of essential safety functions, passive technology with inherent safety features has been generally applied to the design of advanced nuclear power plant. The PWR (pressurized water reactor) NPP (nuclear power plant) in this paper is a kind of mature pressurized water plants in China, and is proposed to be improved with some passive systems to enhance safety performance. The proposed and adapted passive safety systems for this PWR power plant in this paper contain: (1) the RMT (reactor makeup tank);(2) the A-ACC (advanced accumulators);(3) the IRWST (in-containment refueling water storage tank);(4) the PDS (passive depressurization system);(5) the PRHRS (passive residual heat removal system), which is installed on the reactor coolant system (RCS) loop. In this research, the behaviors of passive safety systems are studied and transient characteristics of the primary and secondary side of the reactor during the Steam Generator Tube Rupture (SGTR) accident are investigated using the best-estimate transient simulation code Relap5/MOD3.3. Results reported in this paper indicate that making use of passive safety systems especially the PRHRS could ensure reactor safety during the SGTR accident. Copyright © 2018-2019 by JSME

关键词： Pressurized water reactors

来源：评论

学校读者我要写书评

暂无评论

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

请选择保存的检索档案：

请选择收藏分类：

通借通还

建议与咨询 留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

请选择保存的检索档案： 新增检索档案 确定 取消

请选择收藏分类： 新增自定义分类 确定 取消

通借通还

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

请选择保存的检索档案：

请选择收藏分类：