TY - GEN
T1 - Flow visualization in a simplified Helically coiled steam generator geometry
AU - Lee, Saya
AU - Delgado, Marilyn
AU - Lee, Samuel J.
AU - Hassan, Yassin A.
N1 - Funding Information:
The authors gratefully acknowledge the financial support from Argonne National Laboratory through the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program of the Department of Energy (DOE).
PY - 2017
Y1 - 2017
N2 - Helically coiled steam generators (HCSG) have been considered for new nuclear power plant designs including high temperature gas cooled reactors and small modular reactors. In this study a simplified HCSG design with single flow channel was proposed to generate experimental benchmarking data. The experiment was conducted at Re ≈ 9,000 considering the currently reasonable computing power. The mean velocity and the second order statistics profiles were obtained from multiple locations. Also, the vortex structure was analyzed using Q-criterion. The results showed interactions between rods and flow oscillations. The oscillating rotational flow in cavity regions seemed to be related to the tangential vortical flow structure along the rods. This phenomenon requires additional simultaneous flow visualization from a different angle in further works.
AB - Helically coiled steam generators (HCSG) have been considered for new nuclear power plant designs including high temperature gas cooled reactors and small modular reactors. In this study a simplified HCSG design with single flow channel was proposed to generate experimental benchmarking data. The experiment was conducted at Re ≈ 9,000 considering the currently reasonable computing power. The mean velocity and the second order statistics profiles were obtained from multiple locations. Also, the vortex structure was analyzed using Q-criterion. The results showed interactions between rods and flow oscillations. The oscillating rotational flow in cavity regions seemed to be related to the tangential vortical flow structure along the rods. This phenomenon requires additional simultaneous flow visualization from a different angle in further works.
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M3 - Conference contribution
AN - SCOPUS:85033598064
T3 - 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
BT - 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
PB - International Congress on Advances in Nuclear Power Plants, ICAPP
T2 - 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
Y2 - 24 April 2017 through 28 April 2017
ER -