Research · 02
Computational Fluid Dynamics & Validation
전산유체역학(CFD) 해석 및 검증
We compute velocity and temperature fields where measurement is impractical, and establish how far those numbers hold by putting them against experiment. The longest thread runs through wire-wrapped fuel bundles for sodium-cooled fast reactors.
Card figures are concept diagrams.
Research highlight
Tube-Bundle Cross-Flow (DES)
How far can the cheap computation stand in for the expensive one?
B. Cho · M. Song — Korean Nuclear Society Spring Meeting 2026
Flow crossing the tubes of a steam generator shakes them. Predicting that shaking calls for LES, which is expensive. We measured how far the much cheaper DES can stand in, against wind-tunnel surface-pressure data. It follows the broad shape of the mean, but falls short on the wake-side pressure recovery.
Read moreReduced-Order Model (ROM)
Thirty-three hours of computing, done in thirty-five seconds
B. Cho · C. Song · M. Song et al. — Nuclear Engineering and Technology 58 (2026)
Water crossing the tubes of a steam generator sheds swirling vortices behind them. Computing that flow in full takes more than a day; compressed into 50 representative shapes and carried forward by a neural network, it takes 35.5 seconds.
Read moreHelical Cruciform Fuel (HCF)
A fuel that mixes without grids
H. Moon · M. Song et al. — Physics of Fluids 38, 085111 (2026)
Twist a fuel rod and the coolant mixes itself. We measured the whole three-dimensional velocity field by magnetic resonance velocimetry (MRV), which works on the same principle as a hospital MRI.
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CFD is not a method where a finer mesh eventually yields the right answer. What decides the result is the model standing in for what cannot be resolved directly, turbulence above all. So before a computed number can support a design decision, it has to come with a statement of how well it holds and under which conditions.
The longest-running subject is the wire-wrapped fuel bundle of a sodium-cooled fast reactor, where a wire spiralled around each pin stirs the coolant. We began by establishing what that wire actually does (Nuclear Engineering and Design, 2017), then solved the three-dimensional flow in a JAEA 127-pin bundle and, the same year, carried the RANS methodology up to the full-scale 217-pin bundle of KAERI's PGSFR. There followed where the vortices form (2019), how flow divides among subchannels (2020), what happens when one channel is blocked (2021), whether the cladding holds during design basis events (2024), and how sodium carries heat through a 37-pin bundle in the PLANDTL facility (2023).
The turbulence model is chosen to fit the question. RANS suffices when only the mean field matters, but not when the result is decided by structures that fluctuate in time. The lower plenum of the High Temperature Test Facility was solved with LES (2023); cross flow in a helical coil steam generator was solved with LES and then separated into structures by proper orthogonal decomposition (NTHAS-13, 2024); and the cross flow and vortices induced by a spacer grid were compared side by side with URANS and DES (2025). The solver, too, is chosen per problem: Ansys, OpenFOAM and STAR-CCM+ are all in use.
The last step is to put the result against measurement. Velocity fields of a 19-pin wire-wrapped bundle, measured under index matching, were compared directly with RANS (Annals of Nuclear Energy, 2020), and three-dimensional fields measured by magnetic resonance velocimetry served as validation data for helical cruciform fuel (NURETH-21, 2025). Analyses we publish go through a grid convergence index (GCI) check and uncertainty quantification as part of the procedure. That accumulated procedure was written up as a CFD methodology for next-generation reactor cores (Korean Society for Energy, 2025).
What we work on
- 01Extending the wire-wrapped bundle RANS methodology from 7 pins to a full-scale 217-pin assembly
- 02Identifying the vortices the wire spacer creates and how flow divides among subchannels
- 03Local blockage and cladding integrity during design basis events
- 04LES of the HTTF lower plenum, LES+POD of helical-coil cross flow, URANS vs DES for spacer grids
- 05Validation against index-matched PIV and MRV measurements
- 06A CFD methodology written up for next-generation reactor cores