Large eddy simulation of 5-tube bundle helical coil steam generator test section

Mustafa Alper Yildiz, Elia Merzari, Yassin A. Hassan

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

Helical Coil Steam Generator (HCSG) is a specific type of shell and tube heat exchanger known for having a higher heat transfer coefficient than many other designs. For this reason, they are considered in Small Modular Reactor (SMR) and High Temperature Reactor (HTR) designs. Investigation of flow behavior in HTRs is important for better design. To investigate the flow on the shell side, five rod HCSG test section was built in Texas A&M University. Experiments were conducted at Reynolds number of approximately 9000. The spectral element code NEK5000 was used to do high fidelity large-eddy simulation (LES) of the test section to validate against experimental results. In this paper preliminary simulation results were presented. Pressure drop in preliminary results with seventh and ninth order polynomial expansion was consistent with experimental data.

Original languageEnglish (US)
Title of host publicationComputational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Print)9784888982566
DOIs
StatePublished - Jan 1 2018
Event2018 26th International Conference on Nuclear Engineering, ICONE 2018 - London, United Kingdom
Duration: Jul 22 2018Jul 26 2018

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume8

Other

Other2018 26th International Conference on Nuclear Engineering, ICONE 2018
CountryUnited Kingdom
CityLondon
Period7/22/187/26/18

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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  • Cite this

    Yildiz, M. A., Merzari, E., & Hassan, Y. A. (2018). Large eddy simulation of 5-tube bundle helical coil steam generator test section. In Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 8). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE26-82382