检索结果-内蒙古大学图书馆

Data Driven Control and Learning Systems (DDCLS)

作者： Xinyu Zhao Na Qin Jie Huang Yongchen Miao the Institute of Systems Science and Technology Southwest Jiaotong University Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Harbin Shipping School Harbin China

ISBN: (数字)9781728159225

ISBN: (纸本)9781728159232

In order to settle the complex problem of layout of spatial pipeline, the diameter of pipeline is taken as the distance between adjacent scattered points, and the spatial layout including obstacles is approximated as a three-dimensional diagram of scattered points. A-star algorithm is used to search an optimal pipelines path from the three-dimensional diagram of scattered points. However, when traditional A-star algorithm addresses pre-selected points that are the same cost, it selects pre-selected points randomly. In view of the disadvantages, an adaptive A-star algorithm is proposed based on the traditional A-star algorithm, in this paper. The adaptive A-star algorithm selects more reasonable pre-selected point according to the surrounding environment and situation of pre-selected point , so as to achieve the requirements of the shortest pipeline and the fewest inflection point. Finally, the experimental simulation shows that the adaptive A-star algorithm has better performance than the traditional A-star algorithm.

关键词： Pipelines Path planning Layout Robots Heuristic algorithms Robot kinematics Optimization

来源：评论

学校读者我要写书评

暂无评论

An acceleration technique for method of characteristics based on preconditioning method and CUDA technique 27

An acceleration technique for method of characteristics base...

引用

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

作者： Zheng, Yong Peng, Minjun Ping, A.N. Wei, L.U. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Harbin Heilongjiang China

ISBN: (纸本)9784888983051

The method of characteristics (MOC) with matrix form has more favorable performance compared with its standard application. And the linear algebraic solver affects heavily the computation efficiency. As a Krylov subspace technique, the preconditioned generalized minimal residual algorithm (PGMRES) was proposed to solve the resulting linear system in previous work. To accelerate the iteration process further, the current study utilizes the GPU-based compute unified device architecture(CUDA) technique to program the massively parallel PGMRES. The sparse matrix vector multiplication(SpMV), the most time-consuming operation, was optimized using the coherent visiting and shared memory, which improves the parallel computing performance significantly. Based on the analysis of the numerical feature of the coefficient matrix, two parallel optimization strategies are proposed to deal with the first part of the matrix equation, and the different schemes are utilized to the different parts of the matrix based on the size of row vector, which are expected to improve the throughput of the SpMV operation. The benchmark problem HTTR(i.e. 2D high temperature engineering test reactor benchmark problem) has been simulated to verify the parallel code and evaluate the acceleration performance, and the numerical results demonstrate that the parallel strategies are efficient for the HTTR problem, and the speedup can achieve more than 5.5 times with the optimal strategy. © 2018-2019 by JSME

关键词： Linear systems

来源：评论

学校读者我要写书评

暂无评论

Pipe Routing of reactor Based on Adaptive A* Algorithm Combined With Genetic Algorithm

Pipe Routing of Reactor Based on Adaptive A* Algorithm Combi...

引用

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

Application of feedforward predictive control in DC furnace coordination system

引用

Journal of Physics: Conference Series 2021年第1期1780卷

作者： Zhiguang DENG HE Zhengxi ZHU Biwei ZHU Jialiang LV Xin WU Qian National Key Labortory of Science and Technology on Reactor System Design Technology Chengdu610213China

In order to solve the control difficulties such as large dynamic delay, serious coupling between machine and furnace and strong nonlinear, the feedforward and feedback predictive control is proposed to control the coordinated system on the basis of multi-model predictive control, and the static feedforward part designs the feed line feedforward of coal quantity against coal quality disturbance on the basis of the accurate balance of energy. Thus, the reference total fuel quantity under the target load instruction is determined, and the dynamic part fully considers the dynamic compensation of the unit energy storage, gives a certain overshoot fuel quantity to the boiler regulation, speeds up its response, and ensures the rapidity of the unit. The real-time simulation results of virtual DPU (Distributed Processing Unit) show that the designed feedforward-feedback predictive control can quickly respond to load change, improve the resistance to fuel disturbance, reduce the fluctuation of main steam pressure, and better ensure the safe, economic and stable operation of the coordination system.

关键词：

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

Abnormal flow of α particles in heavy-ion collisions at intermediate energies

引用

Physical Review C 2021年第4期103卷 044607-044607页

作者： G. Qu (曲国峰) Y. Huang (黄宇) D. Peng (彭丹) Z. Xu (徐子虚) W. Lin (林炜平) H. Zheng (郑华) G. Tian (田国玉) R. Han (韩瑞) C. Ma (马春旺) M. Huang (黄美容) P. Ren (任培培) J. Han (韩纪锋 ) Z. Yang (杨振雷) X. Liu (刘星泉) R. Wada Key Laboratory of Radiation Physics and Technology of the Ministry of Education Institute of Nuclear Science and Technology Sichuan University Chengdu 610064China School of Physics Henan Normal University Xinxiang 453007 China School of Physics and Information Technology Shaanxi Normal University Xi'an 710119 China Institute of Modern Physics Chinese Academy of Sciences Lanzhou 730000 China College of Physics and Electronics information Inner Mongolia University for Nationalities Tongliao 028000 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610213 China Cyclotron Institute Texas A&M University College Station Texas 77843 USA

The experimentally observed abnormal α flow behavior from heavy-ion collisions at intermediate energies is investigated using the events of Ca40+Ca40 at 35 MeV/nucleon simulated with an improved antisymmetrized molecular dynamics model with specific consideration of the Fermi motion in the nucleon-nucleon collision process. Its possible origins in the processes from the fragment formation to the experimental flow extraction, i.e., dynamical process, sequential decay, experimental detection, and data analysis, are closely examined. It is found that the observed abnormal α flow behavior originates from the reconstruction of reaction planes in the flow extraction. How the abnormal α flow behavior is generated from the reaction plane reconstruction procedure is discussed.

关键词： Collective flow Low & intermediate energy heavy-ion reactions Models & methods for nuclear reactions

来源：评论

学校读者我要写书评

暂无评论

Transcending the MAX phases concept of nanolaminated early transition metal carbides/nitrides – the ZIA phases

arXiv

引用

arXiv 2023年

作者： Tunes, M.A. Drewry, S.M. Schmidt, F. Valdez, J.A. Schneider, M.M. Kohnert, C.A. Saleh, T.A. Schön, C.G. Fensin, S. El-Atwani, O. Goossens, N. Huang, S. Vleugels, J. Maloy, S.A. Lambrinou, K. Materials Science and Technology Division Los Alamos National Laboratory United States Department of Materials Science and Engineering University of Tennessee United States Department of Nuclear Engineering University of California Berkeley United States Materials Physics and Applications Division Los Alamos National Laboratory United States Department of Metallurgical and Materials Engineering Universidade de São Paulo Brazil Reactor Materials and Mechanical Design Pacific Northwest National Laboratory United States Department of Materials Engineering KU Leuven Belgium School of Computing and Engineering University of Huddersfield United Kingdom

A new potential class of nanolaminated and structurally complex materials, herein conceived as the Zigzag IntermetAllic (ZIA) phases, is proposed. A study of the constituent phases of a specific Nb–Si–Ni intermetallic alloy revealed that its ternary H-phase, i.e., the Nb3SiNi2 intermetallic compound (IMC), is a crystalline solid with the close-packed fcc Bravais lattice, the 312 MAX phase stoichiometry and a layered atomic arrangement that may define an entire class of nanolaminated IMCs analogous to the nanolaminated ceramic compounds known today as the MAX phases. The electron microscopy investigation of the Nb3SiNi2 compound – the first candidate ZIA phase – revealed a remarkable structural complexity, as its ordered unit cell is made of 96 atoms. The ZIA phases extend the concept of nanolaminated crystalline solids well beyond the MAX phases family of early transition metal carbides/nitrides, most likely broadening the spectrum of achievable material properties into domains typically not covered by the MAX phases. Furthermore, this work uncovers that both families of nanolaminated crystalline solids, i.e., the herein introduced fcc ZIA phases and all known variants of the hcp MAX phases, obey the same overarching stoichiometric rule Px+yAxNy, where x and y are integers ranging from 1 to 6. © 2023, CC BY.

关键词： Electron microscopy

来源：评论

学校读者我要写书评

暂无评论

The study of radiation effect on Raman Distributed optical fiber Temperature Sensor

引用

Journal of Physics: Conference Series 2021年第1期1780卷

作者： Meiqiong Xiang Yanyang Liu Xianguo Qing Zhengxi He Jialiang Zhu Peng He XinLv Science and Technology on Reactor System Design Technology LaboratoryNuclear Power Institute of China Chengdu610213China

The rapid development of big data and artificial intelligence technology is inseparable from the acquisition of massive basic data, and the data is acquired by sensors. The Raman Distributed optical fiber Temperature Sensor (RDTS) is a kind of sensor with many advantages, such as: anti-electromagnetic interference, intrinsic safety, small size, water and high temperature resistance. It has been applied in many fields for fast and continuous temperaturemeasurement. However, due to the rapid attenuation of transmitted light and the temperature error in radiated environment, it has not been applied innuclear field. Therefore, in order to improve the temperature accuracy of RDTS in radiated environment and provide basic data for advanced control. This paper studies the radiation effect on RDTS. Analyzesthe radiation damage mechanism and radiation damage influencing factors of RDTS. Proposes measures to improve the anti-radiation performance and provides four useful calibration methodsfortemperature error. Among them, two calibration methods have been proved right by experiments.

关键词：

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：