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Error analysis and control of the acoustic overlapping mesh technique

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

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Analysis of contribution degree of vibration transmission of bolted structure 29

Analysis of contribution degree of vibration transmission of...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Liu, Shuai Li, Wanyou Huang, Xuan Xiong, Furui Jiang, Xiaozhou Deng, Dliwei Harbin Engineering University Harbin China Science and Technology on Reactor System Design Technology Laboratory Chengdu China Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9780791886359

In practical engineering, the vibration transmission between bolted structures supported by cantilever beams involves many factors, including the friction between plates and the bolt connection relationship. The vibration transmission effect is the embodiment of the coupling of various factors, so it is impossible to accurately and quantitatively evaluate the influence degree of various factors. In this paper, the influence factors of vibration between bolted plates in the form of cantilever beam are studied by numerical calculation method. The effects of friction coefficient, bolt preload, temperature and internal and external pressure on vibration characteristics are studied. Finally, the contribution of different influencing factors to vibration transmission is given. The preliminary research shows that the bolt connects the two plates into a whole structure, and its stiffness changes little with the friction coefficient, bolt preload, temperature and internal and external pressure. The natural frequency of each order increases with the increase of friction coefficient, bolt preload and internal and external pressure, decreases with the increase of temperature, and the overall trend changes little. At the same time, the bolt preload is verified by test, the difference of natural frequency under the same preload is compared and analyzed, the numerical calculation is compared with the test value, and the vibration contribution of preload is verified. © 2022 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Cantilever beams

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Research Progress of Metal-Based Shielding Materials for Neutron and Gamma Rays

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Acta Metallurgica Sinica(English Letters) 2021年第12期34卷 1609-1617页

作者： Bin Gan Shichang Liu Zhen He Fucai Chen Haoxuan Niu Jingchang Cheng Bo Tan Bo Yu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu610213China State Key Laboratory of Light Alloy Casting Technology for High-End Equipment Shenyang Research Institute of Foundry Co.Ltd.Shenyang110022China

The radiation generated by nuclear reaction is harmful to human body and equipment,thus the radiation shielding materials that employ the shielding ability from neutron and gamma rays are the best candidates according to application situations and radiation *** this paper,the researches of metal-based neutron and gamma rays or multiple purpose shielding materials are systematically summarized,and the respective and principal problems of these materials with respect to shielding effectiveness and other performances,such as corrosion,mechanical properties,manufacture,etc.,are ***,the prospect of shielding materials is outlined,which suggests that the development of highly efficient and multiply functional radiation shielding materials with good environmental compatibility is one of the future development trends.

关键词： Radiation shielding materials Metal-based Boron-containing shielding materials High density alloys

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Abstract

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应用力学学报 2015年第1期32卷 I0001-I0016页

作者： Feng Zhipeng Zang Fenggang Zhang Yixiong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 610213 Chengdu China

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The stress indices study for the pipe with trunnion welding attachment 27

The stress indices study for the pipe with trunnion welding ...

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

作者： Lu, Xifeng Bai, Xiaoming Zheng, Liangang Zhang, Rui Yuan, Feng Yuan, Yanli Huang, Qian Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China

ISBN: (纸本)9784888983051

In the nuclear power plant, the trunnion welding attachment is widely used to connect the pipe and support. According to ASME Code Cases the stress caused by the welded attachment is considered as the additional stress of the pipe. However, the calculation of the additional stress is very complex and time-consuming. A method based on the concept of stress indices is proposed in present work. To investigate the influence of size and constraint and the stress indices, the finite element analysis for pipe with different sizes trunnion welding attachment under different constraint forms are done. The stress indices are calculated for each case, respectively. Furthermore, the fitted expressions for stress indices are proposed for general case. To verify this method, an analysis according to ASME Code Case for piping with trunnion is done. The comparison of the result between present method and the ASME Code Case method show slight different. Therefore, the stress indices method for the stress analysis of pipe with trunnion welding attachment can be an alternative method for ASME Code Cases. The advantage of present method in that it simplified the analysis process by introduces the stress indices. This method is effective and practical during the design and analysis of piping system in the nuclear power plant. Copyright © 2019 by JSME

关键词： Welding

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Model development of Uo2-zr Plate-Type fuel behavior at early phase of severe accident and molten fuel meat relocation 16

Model development of Uo2-zr Plate-Type fuel behavior at earl...

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16th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2015

作者： Zhuohua, Zhang Shinian, Peng Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China

ISBN: (纸本)9781510811843

According to former study on oxygen diffusion, Nb-Zr solid reaction and Uo2-zr solid reaction, models of oxidation, solid reaction in fuel meat and relocation of molten fuel meat are developed based on structure and material properties of Uo2-zr plate. The new models can supply theoretical elements for safety analysis of core assembled with dispersion plate-type fuel under severe accident.

关键词： Uranium dioxide

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Uncertainty quantification research of reactor system under seismic load 27

Uncertainty quantification research of reactor system under ...

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

作者： Huang, Qian Xiong, Furui Bai, Xiaoming Yu, Xiaofei Zheng, Liangang Lu, Xifeng Song, Haiyang Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China

ISBN: (纸本)9784888983051

In the dynamic analysis of reactor system, the key mechanical input parameters are uncertain due to the design change, manufacturing, installation and calculation deviation, which affects the dynamic response, load distribution and final mechanical evaluation results. In order to quantify the influence of the uncertainty on seismic responses and load distribution, the uncertainty quantification of key structural input parameters of reactor system under seismic load is studied. Firstly, according to the fundamental characters of key input parameters (contact stiffness and gap among various assemblies), maximum entropy principle is adopted to construct the probability density function(PDF). Then, Markov Chain Monte Carlo technique is applied to sample according to the PDF, and the input and output data pool is constructed via finite element transient computations. According to the results, probabilistic distributions of dynamic responses caused by uncertainty from inputs parameters are evaluated and the reliability of nominal model is investigated. The studies show that the probabilistic distribution of reactor system dynamic response differs greatly with different output mechanical parameters, degrees of freedom and frequency bands. The uncertainty quantification method and process for reactor system are proposed in this paper. This method can be extended to other equipments easily. Therefore, it is an effective tools for the reliability of dynamic response. Copyright © 2018-2019 by JSME

关键词： Markov processes

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Prediction of the critical heat flux in subcooled flow boiling in round tube using an improved mechanistic model

Prediction of the critical heat flux in subcooled flow boili...

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18th International Conference on Nuclear Engineering, ICONE18

作者： Na, Yu Yu, Zhang National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute of China Chengdu Sichuan 610041 China

ISBN: (纸本)9780791849323

Among the existing CHF models, the bubble crowding model and the liquid sublayer dryout model have been well accepted for subcooled flow boiling. But both of the two models couldn't give explanation about some details in the boiling crisis phenomenon according to photographic result. The aim of the present paper is to provide an improved synthesized model containing the characteristic of the above two models and then to give a comprehensive explanation about CHF. In the present model, the conservation equations of mass and energy are solved to derive the CHF formula. The length and velocity of the vapor blanket and the thickness of the liquid sublayer are needed. The quality and void fraction in bubble region and the core region are calculated by a homogeneous assumption. The vapor blanket length is thought to be equal to the Helmholtz wavelength and it is obtained from several parameters in the bubble region. The velocity of the vapor blanket is connected to the flow velocity of the bubble layer. The thickness of the sublayer is determined by a force balance on the vapor blanket, which is also related to the condition of the bubble region. About 1100 experimental points have been selected to verify the proposed model. Comparison between the predictions by the proposed model and the experimental result shows a good agreement that more than 90% of these data are predicted within ±20%. © 2010 by ASME.

关键词： Void fraction

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THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONICS with COMSOL and RMC 29

THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONIC...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Liu, Zhenhai Qi, Feipeng Zhou, Yi Li, Quan Chen, Ping Chen, Hao Ma, Chao Zhao, Bo Li, Chenxi Science and Technology on Reactor System Design Technology Laboratory Npic Chengdu China

ISBN: (纸本)9780791886366

Predicting fuel behavior in the reactor is a typical multiphysics coupling problem. The traditional fuel performance analysis adopts a decoupling way. To provide a higher fidelity tool for fuel performance simulation, the multi-physics coupling software COMSOL and 3D Monte Carlo neutron transport code RMC are coupled. The fuel rod thermo-mechanical coupling analysis module is constructed in COMSOL. RMC is innovatively wrapped as a component of COMSOL to communicate with the fuel performance module. Grid mapping algorithm is set up using COMSOL's functionality. A carefully designed segregation solver sequence is used to control the coupling process. The fine power distribution calculated by RMC is transferred to COMSOL fuel thermal calculation, and the fuel temperature and the coolant temperature and density calculated by COMSOL are transferred to RMC. In a Picard iterative way, the fuel rod lattice level neutron thermomechanical tight coupling is realized. The coupling is demonstrated in a fuel rod BOL steady state case. The fuel performance analysis is enhanced by the higher fidelity neutron flux solution. © 2022 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Iterative methods

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key technology of a New Potential Economical Desalination Method for Small Nuclear Power 23rd

Key Technology of a New Potential Economical Desalination Me...

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23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Li, Siguang Gan, Yiran Li, Yi Liang, Tiebo Science and Technology on Reactor System Design Technology Laboratory Sichuan Chengdu China

ISBN: (纸本)9789811988981

With the rapid development of distributed energy, small nuclear power has been widely concerned by researchers because of its inherent advantages. Keeping circulating water in a low salinity state is an important factor in economically maintaining the system operation. Therefore, it is necessary to investigate a specialized desalination method for small nuclear power. In this paper, expert knowledge and comparative analysis were introduced to study the advantages and disadvantages of some traditional desalination methods according to the recent requirements for small nuclear power. In addition, a potential economical namely hydrate-based desalination method was discussed, the key technologies that are urgent to be solved for this method were summarized and one of these technologies, phase equilibria of gas hydrate prediction, was studied using a thermodynamic model. Results show that each traditional desalination method cannot well meet the requirements for economy, energy and environment. Referring to the national requirements for carbon emission, the hydrate-based method is much suitable for small nuclear power due to its significant advantages in the fields of economy, energy and environment. In addition, the proposed thermodynamic model shows good performance compared with the published hydrate equilibrium data. Furthermore, the kinetics of hydrate formation and decomposition is considered another key to promoting the development of hydrate-based method. Finally, we hope the solution to the above problem can provide the idea of designing small nuclear power in the future. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Desalination

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