Numerical investigation of fluid flow in a square channel-versatile test reactor program

Byung Hee Choi, Daniel Orea, Thien Nguyen, N. K. Anand, Yassin Hassan, Piyush Sabharwall

Research output: Contribution to journalConference articlepeer-review

2 Scopus citations

Abstract

We have conducted flow simulations of fluid flow in the proof-of-concept facility using various turbulence models. It is found that the SSG model has the best performance for our configuration when validated against experimental measurements and available databases for the developing flow and fully developed flow in a square channel. The streamwise velocity estimated by the SSG model has a reasonable fit on both PIV measurements and the DNS reference. Secondary vortices can be estimated using the SSG model, and their shape and magnitude are similar to the DNS reference. The TKE is underestimated when compared to the PIV measurements, but it shows the same trends qualitatively. Therefore, we can conclude that SSG is most appropriate turbulence model among these candidate turbulence models. Further numerical simulations of particle transport in the PCF will be performed using the SSG model and Lagrangian approach.

Original languageEnglish
Pages (from-to)1149-1152
Number of pages4
JournalTransactions of the American Nuclear Society
Volume121
DOIs
StatePublished - 2019
Externally publishedYes
Event2019 Transactions of the American Nuclear Society, ANS 2019 - Washington, United States
Duration: Nov 17 2019Nov 21 2019

Funding

This work is performed under the U.S. Department of Energy Office of Nuclear Energy’s Versatile Test Reactor program.

FundersFunder number
Office of Nuclear Energy

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