The core inlet flow rates and exit pressure distributions of an APR+ (Advanced Power Reactor Plus) reactor were evaluated experimentally in this study. The tests were performed in the ACOP (APR+ Core Flow & Pressure) test facility constructed with a linear reduced scale of 1/5 referring to the prototype plant. The major flow path inside the reactor vessel was designed with a preservation of a geometrically similar flow without hindering the dynamic similarity. The 257 core simulators with 771 pressure impulse lines were installed in the ACOP facility to measure the hydraulic characteristics at the inlet and outlet of the fuel assemblies. The pressure distributions along the major flow path were obtained by measuring the static pressure and differential pressures at 584 points. The hydraulic characteristics of the reactor flow under an unbalanced cold leg flow condition were investigated by using an ensemble averaging process of 5 independent tests. The details of these experiments and a data analysis were described in this paper.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5581-2
PROCEEDINGS PAPER
APR+ Core Flow and Pressure Distributions Under the 4 Pump Unbalanced Flow Condition
K. Kim,
K. Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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D. J. Euh,
D. J. Euh
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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Y. J. Youn,
Y. J. Youn
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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I. C. Chu,
I. C. Chu
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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H. S. Choi,
H. S. Choi
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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T. S. Kwon
T. S. Kwon
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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K. Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
D. J. Euh
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Y. J. Youn
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
I. C. Chu
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
H. S. Choi
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
T. S. Kwon
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Paper No:
ICONE21-15608, V004T09A049; 8 pages
Published Online:
February 7, 2014
Citation
Kim, K, Euh, DJ, Youn, YJ, Chu, IC, Choi, HS, & Kwon, TS. "APR+ Core Flow and Pressure Distributions Under the 4 Pump Unbalanced Flow Condition." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 4: Thermal Hydraulics. Chengdu, China. July 29–August 2, 2013. V004T09A049. ASME. https://doi.org/10.1115/ICONE21-15608
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