检索结果-内蒙古大学图书馆

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

作者： Liu, Hang Huang, Haojie Lai, Jianyong Pan, Liangming Li, Yi Zhou, Wenxiong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Nanjing Research Institute of El ectronics Technology Nanjing210000 China Department of Nuclear Engineering Chongqing University Chongqing400044 China

ISBN: (纸本)9784888983051

Interfacial area concentration is one of the most critical parameters in two-phase flow and reflects the interfacial area of mass, momentum and energy transfer. The prediction of interfacial area concentration is also essential to close the interfacial transfer terms in the two-fluid model. The calculation of interfacial area concentration has been well developed from bubbly flow to churn flow, including interfacial area correlations and two-group interfacial area transport equation. While seldom researchers focus on that for annular flow or annular mist flow. This paper proposed the one-dimensional interfacial area correlation for annular flow in vertical pipes based on the averaged liquid film thickness model for annular flow. The effects of the droplets in pipes were also considered in the model. The new model has been evaluated against the existing experimental data. The results indicate that the new model can provide the excellent prediction of the interfacial area concentration for annular flow in vertical pipes. Copyright © 2018-2019 by JSME

关键词： Two phase flow

来源：评论

学校读者我要写书评

暂无评论

Phase distribution characteristics of cap bubbly flow in 5×5 rod bundles with mixing vane spacer grids 27

Phase distribution characteristics of cap bubbly flow in 5×...

引用

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

作者： Ren, Quan-Yao Pu, Zeng-Ping Pan, Liang-Ming Zheng, Mei-Yin Wang, Hao-Yu Zhou, Wen-Xiong Wei, Lie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Key Laboratory of Low-grade Energy Utilization Technologies and Systems Chongqing University Ministry of Education Chongqing400044 China

ISBN: (纸本)9784888983051

To improve the understanding on the mechanisms of phase distribution and bubble interaction for cap bubbly flow in rod bundles, the adiabatic upward cap bubbly flow has been investigated experimentally in 5×5 rod bundles with prototypical mixing vane spacer grids (MVSGs). Miniaturized four-sensor conductivity probe (MFSCP) has been developed to measure the local two phase flow parameters, such as void fraction, interfacial area concentration (IAC), bubble velocity, and bubble chord length. The detailed local parameters in cap bubbly flow has been measured and analyzed, based on which the phase distribution characteristics have been analyzed for Group I and II bubbles in detail. Moreover, the axial development and the effect of MVSG have also been analyzed. Some interesting phenomenon have been observed: Group I void fraction profile is almost flat at the measuring line while Group II void fraction profile has the skewed peaks near the sub-channel center resulted for the limitation of rod walls and the strong secondary flow;Group I IAC is the main contribution to the total IAC, whose profile has the peaks near the rod gap due to the smaller bubble size near the rod walls. For current cap bubbly flow condition, the bubble velocity and size are the two determined factors for Group I IAC for the similar void fraction, while the void fraction is the key factor for Group II IAC for the larger bubble size. Furthermore, because of the shear force of MVSG and induced stronger turbulence, the large Group II bubbles break up into Group I bubbles and smaller Group II bubbles, which results in the smaller bubble size and larger Group I void fraction and IAC. According to the analysis on the axial development of local parameter profiles, the MVSG dissipation length might be larger than 19.4 L/Dh, but smaller than 32.1 L/Dh for current cap bubbly flow condition. Copyright © 2018-2019 by JSME

关键词： Void fraction

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

Adding a third level of parallelism to OpenMOC, an open source deterministic neutron transport solver

Adding a third level of parallelism to OpenMOC, an open sour...

引用

2019 International Conference on Mathematics and Computational Methods Applied to Nuclear science and Engineering, M and C 2019

作者： Giudicelli, Guillaume Wu, Wenbin Josey, Colin Smith, Kord Forget, Benoit Nuclear Science and Engineering Department Massachusetts Institute of Technology 77 Massachusetts Avenue Cambridge02139 United States Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Los Alamos National Laboratory New Mexico United States

来源：评论

学校读者我要写书评

暂无评论

Determining impact parameters of heavy-ion collisions at low-intermediate incident energies using deep learning with convolutional neural networks

引用

Physical Review C 2022年第3期105卷 034611-034611页

作者： X. Zhang (张鑫) X. Liu (刘星泉) Y. Huang (黄宇) W. Lin (林炜平) H. Zheng (郑华) R. Wada A. Bonasera Z. Chen (陈志强) L. Chen (陈蕾) J. Han (韩纪锋) R. Han (韩瑞) M. Huang (黄美容) Q. Hu (胡强) Q. Leng (冷强钟) C. W. Ma (马春旺) G. Qu (曲国峰) P. Ren (任培培) G. Tian (田国玉) Z. Xu (徐子虚) Z. Yang (杨振雷) L. Zhang (张丽娜) Key Laboratory of Radiation Physics and Technology of the Ministry of Education Sichuan University Chengdu 610064 China School of Physics and Information Technology Shaanxi Normal University Xi'an 710119 China Cyclotron Institute Texas A&M University College Station Texas 77843 USA Laboratori Nazionali del Sud INFN via Santa Sofia 62 95123 Catania Italy 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 School of Physics Henan Normal University Xinxiang 453007 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610213 China School of Information Sciences and Engineering Lanzhou University Lanzhou 730000 China

A deep learning based method with the convolutional neural network (CNN) algorithm for determining the impact parameters is developed by using constrained molecular-dynamics model simulations, focusing on the heavy-ion collisions at the low-intermediate incident energies from several tens to one hundred MeV/nucleon in which the emissions of heavy fragments with the charge numbers larger than three become crucial. To make the CNN applicable in the task of the impact-parameter determination at the present energy range, specific improvements are made in the input selection, the CNN construction, and the CNN training. It is demonstrated from the comparisons of the deep CNN method and the conventional methods with the impact-parameter-sensitive observables that the deep CNN method shows better performance for determining the impact parameters, especially leading to the capability of providing better recognition of the central collision events. With a proper consideration of the experimental filter effect in both training and testing processes to keep consistency with the actual experiments, the good performance of the deep CNN method holds and performs significantly better in terms of predicting the impact parameters and recognizing the central collision events compared with conventional methods, demonstrating the superiority of the present deep CNN method. The deep CNN method with the consideration of the filter effect is applied in the deduction of nuclear stopping power. Higher accuracy for the stopping power deduction is achieved benefitting from the better impact-parameter determination using the deep CNN method, compared with using conventional methods. This result reveals the importance of selecting a reliable impact-parameter-determination method in the experimental deduction of the nuclear stopping power as well as other observables.

关键词： Low & intermediate energy heavy-ion reactions Convolutional neural networks Machine learning Nuclear data analysis & compilation

来源：评论

学校读者我要写书评

暂无评论

A Reduced-order Extrapolation Model Based on Proper Orthogonal Decomposition Technique for Rayleigh–Bénard convection

A Reduced-order Extrapolation Model Based on Proper Orthogon...

引用

第二届材料科学应用与能源材料国际研讨会

作者： Jinghua Yang Dengfeng Lu Zhiguang Deng Xiang Guan Qing Shi Sichuan Electric Power Design & Consulting Co. Ltd National Key Labortory of Science and Technology on Reactor System Design Technology

In order to quickly calculate the flow characteristics in the simulated two-dimensional Rayleigh–Bénard convection model,a reduced-order extrapolation difference model for solving two-dimensional Rayleigh–Bénard is established based on the Proper Orthogonal Decomposition(POD) ***,the classical difference format is used to calculate the flow field on the initial time span,the sample data is to construct the POD basis,and the truncation error generated in the process of constructing the POD base is ***,the two-dimensional reduced-order extrapolation Rayleigh–Bénard model is constructed by combining the SVD and POD *** numerical examples,the classical difference model and the reduced-order extrapolation model are numerically simulated under the given initial boundary *** reliability and effective of the reduced-order method are verified by comparing the flow field temperature cloud maps in the two calculation stages.

关键词： POD A Reduced-order Extrapolation Model Based on Proper Orthogonal Decomposition Technique for Rayleigh nard convection Model

来源：评论

学校读者我要写书评

暂无评论

The application of Deep Reinforcement Learning in Coordinated Control of Nuclear reactors

引用

Journal of Physics: Conference Series 2021年第1期2113卷

作者： Jing Li Yanyang Liu Xianguo Qing Kai Xiao Ying Zhang Pengcheng Yang Yue (Marco) Yang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610213 China Department of Engineering The University of Sydney Sydney 2006 Australia

The nuclear reactor control system plays a crucial role in the operation of nuclear power plants. The coordinated control of power control and steam generator level control has become one of the most important control problems in these systems. In this paper, we propose a mathematical model of the coordinated control system, and then transform it into a reinforcement learning model and develop a deep reinforcement learning control algorithm so-called DDPG algorithm to solve the problem. Through simulation experiments, our proposed algorithm has shown an extremely remarkable control performance.

关键词：

来源：评论

学校读者我要写书评

暂无评论

Improvements of the CMFD acceleration capability of OpenMOC

Improvements of the CMFD acceleration capability of OpenMOC

引用

2019 International Conference on Mathematics and Computational Methods Applied to Nuclear science and Engineering, M and C 2019

作者： Wu, Wenbin Giudicelli, Guillaume Smith, Kord Forget, Benoit Yao, Dong Luo, Qi Department of Nuclear Science and Engineering Massachusetts Institute of Technology 77 Massachusetts Ave CambridgeMA02139 United States Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China NO. 328 Section 1 Changshun Ave Shuangliu District Chengdu Sichuan Province610213 China

ISBN: (纸本)9780894487699

Due to its computational efficiency and geometrical flexibility, the Method of Characteristics (MOC) has been widely used for light water reactor lattice physics analysis. Usually acceleration methods are necessary for MOC to achieve acceptable convergence on practical reactor physics problems. Among them, Coarse Mesh Finite Difference (CMFD) is very popular and can drastically reduce the number of transport iterations. In OpenMOC, CMFD acceleration was implemented but had the limitation of supporting only a uniform CMFD mesh, which would often lead to splitting MOC source regions, thus creating an unnecessary increase in computation and memory use. In this study, CMFD acceleration with a nonuniform Cartesian mesh is implemented into OpenMOC. We also propose a quadratic fit based CMFD prolongation method in the axial direction to further improve the acceleration when multiple MOC source regions are contained in one CMFD coarse cell. Numerical results are presented to demonstrate the improvement of the CMFD acceleration capability in OpenMOC in terms of both efficiency and stability. © 2019 American Nuclear Society. All rights reserved.

关键词： Acceleration

来源：评论

学校读者我要写书评

暂无评论

Neutron physical feasibility of small modular design of dual fluid reactor 27

Neutron physical feasibility of small modular design of dual...

引用

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

作者： Wang, Xiang Zhang, Qian He, Xun Du, Zhuoqi Seidl, Marcus Macian-Juan, Rafael Czerski, Konrad Dabrowski, Mariusz College of Nuclear Science and Technology Harbin Engineering University Harbin Heilongjiang China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China Institute of Nuclear Engineering Technical University of Munich Garching Bayern Germany Faculty of Mathematics and Physics University of Szczecin Szczecin Poland

ISBN: (纸本)9784888983051

The Dual Fluid reactor (DFR) is a fast reactor concept proposed by the Institute of Solid-state- and Nuclear physics (IFK) in Berlin. The design of DFR aims to combine the Gen-IV Molten Salt reactor (MSR) and the Liquid-Metal Cooled reactor (SFR, LFR), which means that the molten-salt fuel is no more used as coolant while the heat is removed in a separate loop by liquid lead, to improve these two concepts. Without control rods, DFR is given hope to react and take steps to the change of operation conditions automatically by its inertial negative temperature feedback. Since fuel and coolant are both liquid, the circulation speed of each liquid is considered capable to adjust operational parameters for DFR. The original design of a 3000MWth (Wang, 2017) and a downscaled version of 500MWth (He, 2016) were analyzed in the aspects of reactor physics and thermal-hydraulics. For the practical purpose, this paper has proposed a small modular version of the DFR, which has power output of 2MWth. The reactor with such power level is expected in various applications. Therefore, it is necessary to perform the more explicit analysis on the design than the previous ones. The analysis focuses on the neutronic calculations with the default fuel salt of U-Pu mixture under steady state conditions. Copyright © 2018-2019 by JSME

关键词： Coolants

来源：评论

学校读者我要写书评

暂无评论

A method for predicting the configuration of corium pool in RPV lower plenum

A method for predicting the configuration of corium pool in ...

引用

2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018

作者： Liu, Lili Yu, Hongxing Chen, Liang Jian, Deng Chunrui, Deng Dan, Zhang Xiaoli, Wu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780894487552

The configuration of a corium pool in the lower plenum of reactor vessel is very important for validity of maintaining reactor vessel integrity under IVRERVC (In-Vessel corium Retention through External reactor Vessel Cooling) condition. A method is designed to predict the configuration of corium pool for an Advanced China PWR, call ACP1000 after entire melt dropping into the lower plenum. It takes into account both thermo-chemical reaction of oxides and metals in corium and the influence of different paths of corium relocated from core region into the lower plenum. The reasons why a three-layer pool has not been observed in the MASCA and COSMOS tests are given by this method. The method is applied to investigate the corium configuration of ACP1000 after a hypothetical station blackout (SBO) accident. It is shown that the stratification of the corium pool is related to the relocation paths of the corium. In the case of downward relocation, a two-layer melt pool with a metal layer on the top is formed. For the sideward relocation, the configuration shows a stratified pool consisting of a dense metal layer on the bottom, an oxide layer in the middle and a light metal layer on the top. © 2018 American Nuclear Society. All rights reserved.

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：