Nuclear Power Plant Prestressed Concrete Containment Vessel Structure Monitoring during Integrated Leakage Rate Testing Using Fiber Bragg Grating Sensors

As the last barrier of nuclear reactor, prestressed concrete containment vessels (PCCVs) play an important role in nuclear power plants (NPPs). To test the mechanical property of PCCV during the integrated leakage rate testing (ILRT), a fiber Bragg grating (FBG) sensor was used to monitor concrete s...

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Bibliographic Details
Published in:Applied sciences 2017-04, Vol.7 (4), p.419
Main Authors: Li, Jinke, Liao, Kaixing, Kong, Xianglong, Li, Shengyuan, Zhang, Xinwang, Zhao, Xuefeng, Sun, Changsen
Format: Article
Language:English
Subjects:
Bragg gratings
Containment
Containment vessels
fiber Bragg grating (FBG)
Finite element method
finite element method (FEM)
integrated leakage rate test (ILRT)
Leakage
Monitoring
Nuclear power plants
Nuclear reactor containment
Nuclear reactors
Prestressed concrete
prestressed concrete containment vessel (PCCV)
Sensors
structure health monitoring (SHM)
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Summary:As the last barrier of nuclear reactor, prestressed concrete containment vessels (PCCVs) play an important role in nuclear power plants (NPPs). To test the mechanical property of PCCV during the integrated leakage rate testing (ILRT), a fiber Bragg grating (FBG) sensor was used to monitor concrete strain. In addition, a finite element method (FEM) model was built to simulate the progress of the ILRT. The results showed that the strain monitored by FBG had the same trend compared to the inner pressure variation. The calculation results showed a similar trend compared with the monitoring results and provided much information about the locations in which the strain sensors should be installed. Therefore, it is confirmed that FBG sensors and FEM simulation are very useful in PCCV structure monitoring.
ISSN:2076-3417
2076-3417
DOI:10.3390/app7040419