The main causes of invalidation of heat transfer piping are stress, thermal displacement and vibration in fast reactor. Strain and displacement measurements are of particular importance in the commissioning and running periods, which is to ensure safety of nuclear reactor. The defect and abnormity of sodium piping can be discovered betimes by the strain and displacement measurements, and the hidden problems of piping can be avoided. Based on the investigation of measurement on piping of power plant, the strain and thermal displacement measurements are carried into execution on the main cooling systems of secondary circuit and the accident residual heat removal system of China Experimental Fast Reactor(CEFR) during the commissioning and running periods. According to the measure data, the accurateness of pipe stress analysis is validated, and the security of systems can be safeguarded. This paper describes the strain and displacement measurement on the high-temperature sodium piping, including the measure method for the double-layer piping, the test of detection capability of high temperature strain gauges, displacement measure device, the analysis and adjustment method of measure data, and so on.
Skip Nav Destination
2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5579-9
PROCEEDINGS PAPER
The Measurement of the High Temperature Sodium Pipe in CEFR
Huajin Yu,
Huajin Yu
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Long Tang,
Long Tang
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Min Qi,
Min Qi
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Yuanwu Ye
Yuanwu Ye
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Huajin Yu
China Institute of Atomic Energy, Beijing, China
Long Tang
China Institute of Atomic Energy, Beijing, China
Min Qi
China Institute of Atomic Energy, Beijing, China
Yuanwu Ye
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE21-15853, V002T05A025; 6 pages
Published Online:
February 7, 2014
Citation
Yu, H, Tang, L, Qi, M, & Ye, Y. "The Measurement of the High Temperature Sodium Pipe in CEFR." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors. Chengdu, China. July 29–August 2, 2013. V002T05A025. ASME. https://doi.org/10.1115/ICONE21-15853
Download citation file:
9
Views
Related Proceedings Papers
Related Articles
RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test
ASME J of Nuclear Rad Sci (January,2020)
Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage
ASME J of Nuclear Rad Sci (January,2022)
New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment
ASME J of Nuclear Rad Sci (January,2022)
Related Chapters
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Threshold Functions
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Achievements, Challenges, and Opportunities
Computer Vision for Structural Dynamics and Health Monitoring