检索结果-内蒙古大学图书馆

30th International Congress on Sound and Vibration, ICSV 2024

作者： Wang, Yu Lai, Jian-Yong Cai, Long-Qi Li, Zhao-Wen Liu, Jia Wang, Ran Liu, Shuai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789090390581

As an important noise source for nuclear power systems, pump equipment needs continuous operation and always in a high vibration level. With the development of vibration isolation technology, floating raft vibration isolation is increasingly favored by people as a new and effective vibration control method. At present, the research on the floating raft vibration isolation system mostly focuses on the influence of the basic stiffness, the damping, and the mass-ratio. And there were few studies on the structural style of the floating raft. In order to explore the effects of the structural parameters on the vibration characteristics of floating raft system. The floating raft vibration isolation system of the pump equipment was researched in this paper. The finite element analysis model of the floating raft vibration isolation system was established by ANSYS. And the Control-Variable method was used to explore the effects of parameters such as the elasticity and density of the raft structure. © 2024 Proceedings of the International Congress on Sound and Vibration. All rights reserved.

关键词： Nuclear energy

来源：评论

学校读者我要写书评

暂无评论

Annealing-induced gradient nanostructured FeCrAlTiMo high-entropy alloy coatings with significantly enhanced wear resistance

引用

Tungsten 2024年第3期6卷 544-548页

作者： Jian Yang Ming-Yang Zhou Ji-Jun Yang Key Laboratory of Radiation Physics and Technology of Ministry of Education Institute of Nuclear Science and TechnologySichuan UniversityChengdu 610064China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

Recently,the amorphous high-entropy alloy(HEA)coatings exhibit an impressive resistance to the lead–bismuth eutectic(LBE)corrosion and ion irradiation,showing great application potential for lead-cooled fast reactors... 详细信息

关键词： alloy resistance wear

来源：评论

学校读者我要写书评

暂无评论

Investigations on friction resistance of forced circulation in a circular tube under inclination and rolling conditions

Investigations on friction resistance of forced circulation ...

引用

18th International Conference on Nuclear Engineering, ICONE18

作者： Du, Sijia Hong, Zhang Department of Engineering Physics National Key Laboratory of Science and Technology on Reactor System Design Technology of Nuclear Power Institute of China China National Key Laboratory of Science and Technology on Reactor System Design Technology of Nuclear Power Institute of China China

ISBN: (纸本)9780791849323

The friction resistance under marine conditions is very important to a marine reactor system in the ocean. The traditional empirical or semi-empirical relationships were used in thermo-hydraulic system programmes at the present time, while the applicability of these relationships under ocean conditions was not validated adequately. Experiments have been conducted to study the friction resistance of forced circulation when the test tube was at inclined attitude and rolling model. The experimental setup consists of stainless steel cylinder tube as test section with 10mm inside diameter and 1200mm length, is subjected to a constant wall heat flux boundary condition. The investigation covers Reynolds number range from 1.0e+4 to 1.2e+5, and the test section angles of inclination including 10°, 20°and 30°, amplitudes of rolling angle including 10°, 15°and 20°with the rolling periods of 10s, 15s and 20s. Pressure drop was measured to calculate the coefficient of friction resistance. CFD method was used to simulate the flow characteristics under inclination and rolling conditions, the results were compared with experimental data. The investigations showed that the influence of inclination and rolling to friction coefficient is not obvious. © 2010 by ASME.

关键词： Reynolds number

来源：评论

学校读者我要写书评

暂无评论

Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix

引用

Annals of Nuclear Energy 2025年 222卷

作者： Yiwen Chen Qi Lu Changwen Liu Wei Li Dalin Zhang G.H. Su State Key Laboratory of Multiphase Flow in Power Engineering Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology School of Nuclear Science and Technology Xi’an Jiaotong University Xi’an 710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 61213 China State Key Laboratory for Strength and Vibration of Mechanical Structures Xi’an Jiaotong University Xi’an 710049 China

Fully Ceramic Microencapsulated (FCM) fuel, fabricated using 3D printing technology, incorporates traditional Tristructural-Isotropic (TRISO) fuel particles embedded within a 3D-printed SiC matrix. This fuel type shows great potential for compact, high-temperature nuclear reactors. However, comprehensive performance analysis remains challenging due to the multilayered structure, complex material properties, and the irradiation behavior of numerous TRISO particles within the matrix. To address these challenges, this study aims to apply finite element (FE)-based computational homogenization to evaluate the fuel’s thermomechanical properties. First, a detailed finite element analysis (FEA) of a single TRISO particle’s performance was conducted, focusing primarily on the Buffer-IPyC gap size change during irradiation, a critical factor influencing the fuel’s thermal performance. Second, the homogenization of a single TRISO particle was performed using FEA, accounting for the changes in the Buffer-IPyC gap size. Finally, homogenized TRISO particles were randomly distributed and perfectly bonded within a 3D-printed SiC matrix to form a Representative Volume Element (RVE). The FE homogenization of the RVE was then conducted to derive the effective thermomechanical properties of the FCM fuel. The packing fraction of TRISO particles in the matrix ranged from 10 % to 50 %, with temperature and burnup conditions spanning 800–1600 K and 0–16 % FIMA, respectively. Results show that irradiation significantly affects the effective properties of the fuel, though this impact diminishes as burnup increases. Additionally, the effective thermal conductivity of the FCM fuel decreases with increasing TRISO packing fraction, assuming the thermal conductivity of the SiC matrix exceeds that of TRISO particles. This study provides a valuable reference for the design and optimization of FCM fuel for future nuclear applications.

关键词： Thermal conductivity of solids

来源：评论

学校读者我要写书评

暂无评论

Error analysis and control of the acoustic overlapping mesh technique

引用

Applied Acoustics 2025年 238卷

作者： Wang, Youjiang Yang, Zhuangtao Liu, Zhenghao Ding, Yongle Zhang, Tao Zhang, Daiyu Yu, Long Key Laboratory of Marine Intelligent Equipment and System Ministry of Education Shanghai200240 China School of Ocean & Civil Engineering Shanghai Jiao Tong University Shanghai200240 China Kunming Branch of the 705 Research Institute China State Shipbuilding Corporation Limited Kunming China School of Marine Science and Technology Northwestern Polytechnical University Shaanxi Xi'an China Marine Design and Research Institute of China Shanghai China Xi'an Precision Machinery Research Institute Xi'an China School of Naval Architecture & Ocean Engineering Jiangsu University of Science and Technology Zhenjiang212003 China

Accurate and affordable methods for predicting the underwater radiated noise of ships will facilitate the development of effective noise control techniques. The acoustic overlapping mesh (AOM) technique, which enables the direct integration of volumetric noise terms in the Lighthill and FWH (Ffowcs Williams and Hawking) acoustic analogies, is a promising way to obtain such a method. In this paper, we improved the AOM technique by extending the overlapping mesh idea to the surface noise terms, further reducing the acoustic computational burden. Meanwhile, three causes for numerical errors of the AOM technique are identified and analyzed theoretically and numerically, leading to preliminary guidelines for choosing the acoustic mesh dimensions. The results suggest that keeping the cell-size-to-wavelength ratio (h/λ) lower than 0.05 avoids a sharp increase of the error from Cause-I, and keeping h/λ lower than 0.005 helps maintain this error less than 1 dB. The errors from the other causes (Cause-II and III) can be maintained less than 1 dB by keeping the distance-to-cell-size ratio (r/h) larger than 7.97. The simulation case also shows that the AOM technique reduces the acoustic computational time by more than 99% and 90% for the total and surface noise, respectively, while maintaining a noise prediction difference of around 1 dB. Using a non-uniform acoustic mesh instead of the uniform one helps achieve a much better with a similar acoustic computational time. © 2025 Elsevier Ltd

关键词： Numerical methods

来源：评论

学校读者我要写书评

暂无评论

MATLAB/Simulink-Based Simulation Study of Small Pressurized Water reactor Nuclear Steam Supply system 4

MATLAB/Simulink-Based Simulation Study of Small Pressurized ...

引用

4th Asia Conference on Information Engineering, ACIE 2024

作者： Chen, Jie Xiao, Kai Mengwei, Mengwei Zhao, Zhao Huang, Ke Yang, Pengcheng Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China

ISBN: (纸本)9798350371925

Accurate and reliable modeling and simulation is the key prerequisite for intelligent control technology research of nuclear power plant. For the nuclear steam supply system (NSSS) of small pressurized water reactor under bi-stable steady state operation scheme, this paper firstly establishes the models of the core, regulator, steam generator and other components. Then, the nuclear steam supply system platform (NSSSP) of small pressurized water reactor is built based on Matlab/Simulink. Simulations are carried out to analyze the normal operation transient and load rejection transient in the water supply flow control mode. The accuracy and reliability of NSSSP are verified to beconsistent with the commercial program RETRAN. © 2024 IEEE.

关键词： Simulink

来源：评论

学校读者我要写书评

暂无评论

A combined reactivity control pattern on a floating nuclear power plant 27

A combined reactivity control pattern on a floating nuclear ...

引用

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

作者： Zhou, Bingyan Song, Danrong Chen, Zhang Chai, Xiaoming Xiang, Hongzhi Hu, Yuying Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

In this study, a new combined reactivity control pattern is presented to lower the power peaking factor on a floating nuclear power plant. In the pattern the whole cycle length is divided into several boron-adjusting periods. During one boron-adjusting period, the soluble boron concentration remains unchanged and the core reactivity change is controlled by control rods. Boron concentration would only be changed at the end of a boron-adjusting period. In the whole cycle the boron concentration would be changed for two to four times, which is acceptable for a floating nuclear power plant. To get an optimized solution, a model of the combined reactivity control pattern was established, which contained boron concentration and control rod pattern (CRP) as coupled variables. A particle swarm optimization with novel mutation operator (PSONM) was applied to optimize the solution. The model was practiced based on a small modular reactor ACP100 core. The solution was optimized separately for equal division of two, three, four and five boron-adjusting periods. The results show that the combined reactivity control pattern can get a lower power peak factor than the original rod-controlled-only pattern without shortening the cycle length. Therefore, the safety of the floating nuclear power plant can be improved. Copyright © 2018-2019 by JSME

关键词： Nuclear power plants

来源：评论

学校读者我要写书评

暂无评论

Fatigue crack growth model for edge sliding mode 14

Fatigue crack growth model for edge sliding mode

引用

14th International Conference on Fracture, ICF 2017

作者： Shi, K.K. Zheng, B. Bai, X.M. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

The inherent law between fatigue behaviours of shear-type representative volume element and mode-II fatigue crack growth is found in the range of cycle plastic zone near the crack tip. Prediction models for mode-II fatigue crack growth rate are then proposed by utilizing shear-type low cycle fatigue properties, fatigue failure criterions (plastic strain energy and linear damage accumulation), and effective cycle stress-strain field ahead of the crack tip. Experimental data of two aluminium alloys, 2024-T351 and 7075-T6, are used for models verification. Good agreement between experimental and theoretical results is obtained. © 2017 ICF 2017 - 14th International Conference on Fracture. All rights reserved.

关键词： Fatigue crack propagation

来源：评论

学校读者我要写书评

暂无评论

Study on Acoustic-Induced Vibration (AIV) by reactor coolant pump at secondary support structure 48

Study on Acoustic-Induced Vibration (AIV) by reactor coolant...

引用

48th International Congress and Exhibition on Noise Control Engineering, INTER-NOISE 2019 MADRID

作者： Huang, Xuan Cai, Fengchun Wu, Wanjun Qi, Huanhuan Feng, Zhipeng Liu, Shuai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9788487985317

The reactor coolant pump is the core equipment of nuclear power stations. During the operation of reactor coolant pump, acoustic pulsations are generated due to nonuniform flow within the reactor coolant pump and pass through the main pipe and coolant to the structure in the reactor. The acoustic pulsations can cause the vibration of the structure in the reactor, which is regarded as one of the main reasons of fatigue failure of the structure. In this paper, the finite element model of secondary support structure will be built and verified by test, then the pressure pulsations relation between the reactor coolant pump outlet and the secondary structure will be investigated, the pressure pulsation caused by the reactor coolant was calculated. Finally, the acoustic-induced vibration response of secondary support structure caused by the reactor coolant pump were obtained by harmonic analysis and high circle fatigue analysis will be done on the basis of the results. This study is helpful to understand the acoustic-induced vibration of the reactor coolant pump and to improve the hydraulic design of the reactor coolant pump. © INTER-NOISE 2019 MADRID - 48th International Congress and Exhibition on Noise Control Engineering. All Rights Reserved.

关键词： Harmonic analysis

来源：评论

学校读者我要写书评

暂无评论

Stress intensity factors for penetrate radial cracks in reactor coolant pump flywheel by weight function method 14

Stress intensity factors for penetrate radial cracks in reac...

引用

14th International Conference on Fracture, ICF 2017

作者： Shi, K.K. Zheng, B. Gao, S.Q. Chen, J.G. Lv, X. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

Stress intensity factors for penetrate radial crack at center of keyway and at keyway corner under the plane stress, the plane strain and the three dimensional, based on weight function method, is determined by finite element analysis. Two load cases of pin loading and uniform loading are considered in the present study. About stress intensity factors, finally, an approximate solution and results from weight function method are compared. Several loading are considered that lead to exact solutions which agree with the literature. The accuracy of the analysis has been examined using the finite element method results and were compared to existing solutions for uniform loading in the literature for special geometries, indicating an excellent agreement. © 2017 ICF 2017 - 14th International Conference on Fracture. All rights reserved.

关键词： Stress intensity factors

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：