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In this work, the hybrid vibro-acoustic model reduction technique that is a physical-modal combined formulation is proposed to accelerate the finite element model updating process of the vibro-acoustic pipeline system. Particularly, the new formulation could provide an effective way of the model updating by preserving the physical DOFs for the direct calibration of the undetermined boundary conditions. The sensitivity based vibroacoustic model updating is first conducted, and then the undetermined spring constant at the displacement boundary condition is then directly and effectively calibrated by using the proposed hybrid model reduction formulation. The proposed method is implemented in the real nuclear facility to evaluate its performance. In addition, an experimental implementation test using the inverse force identification process is also conducted to demonstrate the reliability of the generated vibro-acoustic FE model through the proposed method.

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권호기사 목록 테이블로 기사명, 저자명, 페이지, 원문, 기사목차 순으로 되어있습니다.
기사명 저자명 페이지 원문 목차
Generation of security system defense strategies based on evolutionary game theory Bowen Zou, Yongdong Wang, Chunqiang Liu, Mingguang Dai, Qianwen Du, Xiang Zhu p. 3463-3471

Extended cognitive reliability and error analysis method for advanced control rooms of nuclear power plants Xiaodan Zhang, Shengyuan Yan, Xin Liu p. 3472-3482

Real-time measurements and modeling of sodium combustion aerosol dynamics in test chamber to improve the evaluation of SFR containment aerosol behaviour Usha Pujala, Amit Kumar, Subramanian Venkatesan, Sujatha Pavan Narayanam, Venkatraman Balasubramanian p. 3483-3490

Hybrid vibro-acoustic model reduction for model updating in nuclear power plant pipeline with undetermined boundary conditions Hyeonah Shin, Seungin Oh, Yongbeom Cho, Jinyoung Kil, Byunyoung Chung, Jinwon Shin, Jin-Gyun Kim p. 3491-3500

Titanium alloys : a closer-look at mechanical, gamma-ray, neutron, and transmission properties of different grade alloys through MCNPcode application Ghada ALMisned, Omer Guler, Duygu Sen Baykal, G. Kilic, H.O. Tekin p. 3501-3511

(An) efficient numerical modeling approach for coupled electrical cabinets in nuclear power plants Sudeep Das Turja, Md. Rajibul Islam, Dong Van Nguyen, Dookie Kim p. 3512-3527

Effects of microalloying element addition on mechanical properties of SA508 Gr.1A low-alloy steels Se-mi Hyun, Min-Chul Kim, Seokmin Hong, Jongmin Kim, Seok Su Sohn p. 3528-3535

Conceptual RF design of 750 MHz IH cavities for β = 0.10–0.15 ion beams in medical accelerators Jorge Giner Navarro, Gabriela Moreno, Daniel Gavela, Concepción Oliver, Pedro Calvo, Miguel León, Ángel Rodríguez, Ricardo López, José Miguel Carmona, María Alvarado p. 3536-3544

Monte Carlo simulation and optimization of neutron ray shielding performance of related materials Tongyan Cui, Faquan Wang, Linhan Bing, Rui Wang, Zhongjian Ma, Qingxiu Jia p. 3545-3552

Fission counter array for pulse-mode measurements of high-flux and high-energy neutrons Pilsoo Lee p. 3553-3557

Extensive analysis of several Indian and Yemeni soils’ gamma-ray shielding characteristics : an experimental and simulation approach Shamsan S. Obaid, M.I. Sayyed, A.S. Alameen, D.K. Gaikwad, K.A. Mahmoud p. 3558-3565

Optimizing irradiation conditions for natural molybdenum in WWR-K reactor D.S. Sairanbayev, Sh. Kh. Gizatulin, A.N. Gurin, Ye.T. Chakrova, M.T. Aitkulov, A. Zh. Nessipbay, A.Ch. Ashibayev, A.A. Shaimerdenov p. 3566-3570

(A) new surrogate method for the neutron kinetics calculation of nuclear reactor core transients Xiaoqi Li, Youqi Zheng, Xianan Du, Bowen Xiao p. 3571-3584

Study on producing radioisotopes based on fission or radiative capture method in a high flux reactor Wei Xu, Jian Li, Lei Shi p. 3585-3593

Prediction of small-scale leak flow rate in LOCA situations using bidirectional GRU Hye Seon Jo, Sang Hyun Lee, Man Gyun Na p. 3594-3601

Method of the known cross sections for calibration of the fast neutron spectrometer with a single-crystal stilbene based detector I.V. Urupa, E.V. Ryabeva, R.F. Ibragimov, V.D. Sapozhnikov p. 3602-3607

Enhancing X-ray radiation protection with novel liquid silicone rubber composites : a promising alternative to lead aprons Wesam Abdullah, Ramzun M. Ramli, Thair Hussein Khazaalah, Nurul Zahirah Noor Azman, Tasnim M. Nawafleh, Farah Salem p. 3608-3615

Noticeable localized corrosion of solid boric acid on 304 stainless steel Xinzhu Li, Wen Sun, Guiling Ning p. 3616-3625

Uncertainty quantification based on similarity analysis of reactor physics benchmark experiments for SFR using TRU metallic fuel YuGwon Jo, Jaewoon Yoo, Jong-Hyuk Won, Jae-Yong Lim p. 3626-3643

Conceptual design for a 5 kWe space nuclear reactor power system Huaping Mei, Dali Yu, Shengqin Ma, Jiansong Zhang, Yongju Sun, Chao Chen, Meisheng He, Haixia Wang, Yang Li, Liang Wang, Taosheng Li, Jie Yu p. 3644-3653

Solution of OECD/NEA PWR MOX/UO2 benchmark with a high-performance pin-by-pin core calculation code Hyunsik Hong, Jooil Yoon p. 3654-3667

Impact of fuel temperature on nuclear core design calculations Dušan Čalič, Luka Snoj, Marjan Kromar p. 3668-3685

ACE surrogate model-based uncertainty and sensitivity analysis methods for severe accident codes Kwang-Il Ahn p. 3686-3699

High fidelity core flow measurement experiment for an advanced research reactor using a real scale mockup Taeil Kim, Yohan Lee, Donkoan Hwang, WooHyun Jung, Nakjun Choi, Seong Seok Chung, Jihun Kim, Jonghark Park, Hyung Min Son, Kiwon Song, Huiyung Kim, HangJin Jo p. 3700-3716

Identification of primary input parameters affecting evacuation in ventilated main control room through CFAST simulations and application of a machine learning algorithm to replace CFAST model Sumit Kumar Singh, Jinsoo Bae, Yu Zhang, Saerin Lim, Jongkook Heo, Seoung Bum Kim, Weon Gyu Shin p. 3717-3729

Study on the cantilever ratio optimization of high-temperature molten salt pump for molten salt reactor based on structural integrity Xing-Chao Shen, Yuan Fu, Jian-Yu Zhang, Jin Yang, Zhi-Jun Li p. 3730-3739

Life prediction of IGBT module for nuclear power plant rod position indicating and rod control system based on SDAE-LSTM Zhi Chen, Miaoxin Dai, Jie Liu, Wei Jiang, Yuan Min p. 3740-3749

Improved FMM for well locations optimization in in-situ leaching areas of sandstone uranium mines Mingtao Jia, Bosheng Luo, Fang Lu, YiHan Yang, Meifang Chen, Chuanfei Zhang, Qi Xu p. 3750-3757

Evaluating polyester resin as a viable substitute for PMMA in computed tomography dosimetry phantoms A. Khallouqi, A. Halimi, O. El Rhazouani p. 3758-3763

Assessment of environmental fatigue in nuclear power plants : a comparative analysis of the effects of plasticity correction Tae-Song Han, Hee-Jin Kim, Nam-Su Huh, Hyeong-Yeon Lee, Changheui Jang p. 3764-3774

Fission source convergence diagnosis in Monte Carlo eigenvalue calculations by skewness and kurtosis estimation methods Ho Jin Park, Seung-Ah Yang p. 3775-3784

Study on the behavior of radionuclides in geologic samples from fault zone, Gabal Um Hamd, southwestern Sinai, Egypt Doaa M. El Afandy, Eman M. Ibrahim, Ibrahim E. El Aassy, H.A. Abdel Ghany p. 3785-3795

Studies on structural, optical, thermal and low energy shielding for gamma rays for the ZSBP glasses Abeer S. Altowyan, M.I. Sayyed, Ashok Kumar p. 3796-3803

Structural, physical, optical, and gamma ray shielding properties of SnO2-based boro-silicate glasses : the influence of substituting Na2O by SnO2 Mohammad W. Marashdeh, K.A. Mahmoud, Hanan Akhdar, Mohamed Tharwat p. 3804-3811

Flow-induced vibrations of dual-cylinders in axial flow via LES simulations Kangfei Shi, Yu Cao, Zhanying Zheng, Shun Lu, Menglong Liu p. 3812-3825

Implementation of dynamic start-up test experimental data as a main part of the nuclear code validation procedure : developed RELAP5 model for VVER-1000 Navid Vahman, Reza Akbari p. 3826-3834

Pebble flow in the HTR-PM reactor core by GPU-DEM simulation : effect of friction Zuoyi Zhang, Quan Zou, Nan Gui, Bing Xia, Zhiyong Liu, Xingtuan Yang p. 3835-3850

Optimization method for offsite consequence analysis by efficient plume segmentation Seunghwan Kim, Sung-yeop Kim p. 3851-3863

(A) study on modeling of boiling heat transfer in core debris bed of SFR Venkateswarlu S., Hemanth Rao E., Prasad Reddy G.V., Sanjay Kumar Das, Ponraju D., Venkatraman B p. 3864-3871

(The) effect of zinc, iron and manganese content on gamma shielding properties of magnesium-based alloys produced using the powder metallurgy Mesut Ramazan Ekici, Emre Tabar, Gamze Hoşgör, Emrah Bulut, Ahmet Atasoy p. 3872-3883

Understanding the creep behavior of bentonite-sand mixtures as buffer materials in a low-level radioactive waste repository in Taiwan Guo-Liang Ren, Wei-Hsing Huang, Hsin-Kai Chou, Chih-Chung Chung p. 3884-3897

(The) radioactivity levels and beta dose rate assessment from dental ceramic materials in Egypt Mohamed Hasabelnaby, Mohamed Y. Hanfi, Hany El-Gamal, Ahmed H. El Gindy, Mayeen Uddin Khandaker, Ghada Salaheldin p. 3898-3903

Pulse pile-up correction by auto-regression on linear operations (ARLO) method : a comparison with integration-based algorithms Mohammad-Reza Mohammadian-Behbahani p. 3904-3913

Source term inversion of nuclear accidents based on ISAO-SAELM model Dong Xiao, Zixuan Zhang, Jianxin Li, Yanhua Fu p. 3914-3924

Improvement of internal exposure assessments of the inhalation of fuel-type hot particles during long-term outages Moonhyung Cho, Hyeongjin Kim p. 3925-3932

(The) study and design of a deuteron drift tube linear accelerator for middle energy neutron source Tianhao Wei, Yuanrong Lu, Zhi Wang, Meiyun Han, Ying Xia p. 3933-3941

Effect of supplementary cementitious materials on the degradation of cement-based barriers in radioactive waste repository : a case study in Korea Min-Seok Kim, Sol-Chan Han, Jong-Il Yun p. 3942-3949

Coupled 3D thermal-hydraulic code development for performance assessment of spent nuclear fuel disposal system Samuel Park, Nakkyu Chae, Pilhyeon Ju, Seungjin Seo, Richard I. Foster, Sungyeol Choi p. 3950-3960

Discharge characterization of two-region arc plasma (TRAP) ion source Kihyun Lee, Seung Ho Jeong, Tae-Seong Kim, Dae-Sik Chang, Sung-Ryul Huh p. 3961-3968

Material attractiveness of irradiated fuel salts from the Seaborg compact molten salt reactor Vaibhav Mishra, Erik Branger, Sophie Grape, Zsolt Elter, Sorouche Mirmiran p. 3969-3980

참고문헌 (36건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 An enhanced Craig-Bampton method 미소장
2 Substructuring including interface reduction for the efficient vibro-acoustic simulation of fluid-filled piping systems 미소장
3 Advanced Computational Vibroacoustics: Reduced-Order Models and Uncertainty Quantification 미소장
4 Rates of change of eigenvalues and eigenvectors. 미소장
5 Substructuring and model reduction of pipe components interacting with acoustic fluids 미소장
6 A reduction method for structure-acoustic and poroelastic-acoustic problems using interface-dependent Lanczos vectors 미소장
7 Manifestations of the Schur complement 미소장
8 Pseudostatic corrections for the forced vibroacoustic response of a structure-cavity system 미소장
9 Investigations for a model reduction technique of fluid–structure coupled systems 미소장
10 Model reduction methods for cylindrical structures in reactor internals considering the fluid–structure interaction 미소장
11 Reduction of stiffness and mass matrices 미소장
12 An enhanced AMLS method and its performance 미소장
13 FDE index for goodness‐of‐fit between measured and calculated response signals 미소장
14 Root mean square error (RMSE) or mean absolute error (MAE)? – Arguments against avoiding RMSE in the literature 미소장
15 Coupling of substructures for dynamic analyses. 미소장
16 Sensitivity Analysis Methods for Coupled Acoustic-Structural Systems Part I: Modal Sensitivities 미소장
17 Root mean square error (RMSE) or mean absolute error (MAE)? 미소장
18 Seismic analysis of the APR 1400 reactor vessel internals using the model reduction method 미소장
19 A Method of Computation for Structural Dynamics 미소장
20 A general model reduction with primal assembly in structural dynamics 미소장
21 A survey of the state of condition-based maintenance (CBM) in the nuclear power industry 미소장
22 Digital Twin in manufacturing: A categorical literature review and classification 미소장
23 A strongly coupled model reduction of vibro-acoustic interaction 미소장
24 Predicting vibroacoustic performance of thin-walled lightweight structures during conceptual design 미소장
25 The application of machine learning for the prognostics and health management of control element drive system 미소장
26 Digital Twin in the IoT Context: A Survey on Technical Features, Scenarios, and Architectural Models 미소장
27 Multiphysics model reduction of symmetric vibro‐acoustic formulation with a priori error estimation criteria 미소장
28 Prognostics and Health Management in Nuclear Power Plants: An Updated Method-Centric Review With Special Focus on Data-Driven Methods 미소장
29 Development of Vibro-Acoustic Virtual Sensing System for Pipeline Structure Using Digital Twin 미소장
30 Fundamentals of Structural Dynamics 미소장
31 Data-Enabled Physics-Informed Machine Learning for Reduced-Order Modeling Digital Twin: Application to Nuclear Reactor Physics 미소장
32 Multiphysics mode synthesis of fluid–structure interaction with free surface 미소장
33 Prognostic and health management of active assets in nuclear power plants 미소장
34 A real-time unmeasured dynamic response prediction for nuclear facility pressure pipeline system 미소장
35 Real-Time Response Estimation of Structural Vibration with Inverse Force Identification 미소장
36 Implicit inverse force identification method for vibroacoustic finite element model 미소장

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