Validation and application of coupled thermal-hydraulics and neutronics model using sub-channel CFD and SERPENT
File(s)
Published version
Author(s)
Tan, Bryan
Duan, Yu
Bluck, Michael J
Eaton, Matthew D
Liu, Bo
Type
Journal Article
Abstract
The novel coarse-mesh CFD tool Subchannel-CFD (SubChCFD) is coupled with the Monte Carlo transport code Serpent using a segregated multi-physics coupling algorithm. The multi-physics model is validated using the CASL VERA Core Physics Benchmark Progression Problem #6, showing good agreement of pin powers and exit coolant temperatures. The model is also used to simulate an assembly from the K-SMR soluble‑boron-free small modular reactor, which shows good agreement with a full-scale CFD model from the software STAR-CCM+, with the exception of a small gap region between two large control rod guide tube and burnable poison rods, which induces a periodic flow instability that SubChCFD cannot fully replicate. Nevertheless, the oscillatory characteristics of the instabilities modelled by both codes show some similarity.
Date Issued
2026-02-01
Date Acceptance
2025-12-05
Citation
Nuclear Engineering and Design, 2026, 447
ISSN
0029-5493
Publisher
Elsevier
Journal / Book Title
Nuclear Engineering and Design
Volume
447
Copyright Statement
© 2025 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by nc-nd/4.0/).
Subjects
CFD
Publication Status
Published
Article Number
114672
Date Publish Online
2025-12-09