The temperature field at R1/R2 test section in ESPRESSO loop was usually built by the hand-tune way in the past. In this paper, a portable computer measuring and controlling system for temperature field was established to changing the traditional way. And the curves of temperature field, in the situation that the temperature difference were 80°C and 170°C simulate CEFR in-pile in sodium environment of R1/R2 test section, had been set up successfully through the system. Then a thermal shock test was carried out on this basis, and the test purposes were achieved through experiments, which provided necessary condition for subsequent measurement of shape and displacement in core components. It was proved that the system was under good performance by debugging and trial run.
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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 Computer Measuring and Controlling System for Temperature Field of the Thermal-Shock Test at R1/R2 Test Section in ESPRESSO Loop
Fei Zhao,
Fei Zhao
China Institute of Atomic Energy, Beijing, China
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Chunliang Wu,
Chunliang Wu
China Institute of Atomic Energy, Beijing, China
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Fengyang Shen,
Fengyang Shen
China Institute of Atomic Energy, Beijing, China
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Chunxing Gu
Chunxing Gu
China Institute of Atomic Energy, Beijing, China
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Fei Zhao
China Institute of Atomic Energy, Beijing, China
Chunliang Wu
China Institute of Atomic Energy, Beijing, China
Fengyang Shen
China Institute of Atomic Energy, Beijing, China
Chunxing Gu
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE21-15643, V002T05A014; 6 pages
Published Online:
February 7, 2014
Citation
Zhao, F, Wu, C, Shen, F, & Gu, C. "The Computer Measuring and Controlling System for Temperature Field of the Thermal-Shock Test at R1/R2 Test Section in ESPRESSO Loop." 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. V002T05A014. ASME. https://doi.org/10.1115/ICONE21-15643
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