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Copyright © 2022 Han Yong et al. This is an open access article distributed under the Creative Commons Attribution License (the “License”), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License. https://creativecommons.org/licenses/by/4.0/

Abstract

Aiming at vehicles will produce shocks and vibrations for various reasons in the process of transportation and handling, any shock and vibration that exceeds the regulations would cause damage to the nuclear fuel being transported. In order to monitor and analyze the shock and vibration data scientifically, a monitoring system based on MEMS acceleration sensor technology is developed to measure shocks and vibrations. The measured result involves some noise caused by the sensitivity of the sensor and the electrical noise, and a digital filter mathematical modelling is introduced to reduce noise and improve the measured result accuracy. In order to verify the effectiveness of the device designed in this paper, the device and the high-precision seismic acceleration sensor AC73 are, respectively, used for field tests; the results show that the test precision of the designed device can meet the requirements, and also, the designed shock and vibration monitoring system can record and store the three-axis acceleration, temperature, humidity, pressure, time, and other parameters that exceed the set threshold during nuclear fuel transportation in real time and complete the fuel assembly transportation status assessment and promptly remind the transportation personnel to take safety precautions and treatment measures. Therefore, it can be widely used in the monitoring, recording, and postevent data analysis of the transportation process of important products such as nuclear fuel.

Details

Title
The Experimental Validation of a Digital Filter Mathematical Modelling for Nuclear Fuel Vibration Monitoring System
Author
Han, Yong 1   VIAFID ORCID Logo  ; Huang, Shiyong 2   VIAFID ORCID Logo  ; Han MengXuan 3   VIAFID ORCID Logo  ; Zhao, Tao 1   VIAFID ORCID Logo  ; Wen Guang 1   VIAFID ORCID Logo  ; Gu Mingfei 4   VIAFID ORCID Logo  ; Zhang, Qi 5   VIAFID ORCID Logo 

 Chengdu Vocational & Technical College of Industry, Chengdu 610218, China 
 Chengdu China Nuclear Haichuan Nuclear Technology Co., Ltd., Chengdu 610041, China 
 University of Electronic Science and Technology of China, Chengdu 610041, China 
 Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China 
 Chengdu Vocational & Technical College of Industry, Chengdu 610218, China; School of Intelligent Manufacturing, Panzhihua College, Panzhihua 617000, China 
Editor
Miaochao Chen
Publication year
2022
Publication date
2022
Publisher
John Wiley & Sons, Inc.
ISSN
23148896
e-ISSN
23148888
Source type
Scholarly Journal
Language of publication
English
ProQuest document ID
2675434316
Copyright
Copyright © 2022 Han Yong et al. This is an open access article distributed under the Creative Commons Attribution License (the “License”), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License. https://creativecommons.org/licenses/by/4.0/