Numerical implementation of the MOOSE subchannel module (SCM) algorithm

Kyriakopoulos, Vasileios; Tano Retamales, Mauricio Eduardo

doi:10.1016/j.nucengdes.2026.114802

Numerical implementation of the MOOSE subchannel module (SCM) algorithm

Journal Article · Wed Feb 11 00:00:00 EST 2026 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2026.114802· OSTI ID:3020584

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Idaho National Laboratory (INL), Idaho Falls, ID (United States)

The subchannel module of moose (SCM), previously referred to as Pronghorn-SC, is a subchannel code designed to resolve single-phase flow fields and calculate the relevant flow variables, in nuclear reactor fuel-pin assemblies. The assemblies it models are: water-cooled, with bare fuel-pins in a square ducted, quadrilateral lattice and liquid-metal/water-cooled, with bare/wire-wrapped fuel pins in a hexagonal ducted, triangular lattice. Previous publications have presented the development, validation and verification of SCM. This work presents an comparative overview of the different solvers implemented within SCM. This includes the solver algorithm description, and a performance comparison. The two test cases chosen to demonstrate the solver performance were taken from the PSBT enthalpy mixing benchmark and the ORNL-19 pin benchmark.

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 3020584

Report Number(s):: INL/JOU--25-89077

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 450; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (10)

Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters Cheng, Shih-Kuei; Todreas, Neil E. Nuclear Engineering and Design, Vol. 92, Issue 2 https://doi.org/10.1016/0029-5493(86)90249-9	journal	April 1986
A scale analysis of the turbulent mixing rate for various Prandtl number flow fields in rod bundles Kim, Sin; Chung, Bum-Jin Nuclear Engineering and Design, Vol. 205, Issue 3 https://doi.org/10.1016/S0029-5493(00)00382-4	journal	April 2001
The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles Chen, S. K.; Chen, Y. M.; Todreas, N. E. Nuclear Engineering and Design, Vol. 335 https://doi.org/10.1016/j.nucengdes.2018.05.010	journal	August 2018
Validation of Pronghorn’s subchannel code using EBR-II shutdown heat removal tests: SHRT-17 and SHRT-45R Tano, Mauricio; Kyriakopoulos, Vasileios; McCay, James Nuclear Engineering and Design, Vol. 416 https://doi.org/10.1016/j.nucengdes.2023.112783 112783	journal	January 2024
4.0 MOOSE: Enabling massively parallel Multiphysics simulation Harbour, Logan; Giudicelli, Guillaume; Lindsay, Alexander D. SoftwareX, Vol. 31 https://doi.org/10.1016/j.softx.2025.102264	journal	September 2025
Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code Jeong, Hae-Yong; Ha, Kwi-Seok; Chang, Won-Pyo Nuclear Technology, Vol. 149, Issue 1 https://doi.org/10.13182/NT05-A3580	journal	January 2005
Pressure Drop Correlations for Fuel Element Spacers Rehme, Klaus Nuclear Technology, Vol. 17, Issue 1 https://doi.org/10.13182/NT73-A31250	journal	January 1973
Temperature Distribution in the Duct Wall and at the Exit of a 19-Rod Simulated LMFBR Fuel Assembly (FFM Bundle 2A) Fontana, M. H.; MacPherson, R. E.; Gnadt, P. A. Nuclear Technology, Vol. 24, Issue 2 https://doi.org/10.13182/NT74-A31474	journal	November 1974
Development of a Single-Phase, Transient, Subchannel Code, within the MOOSE Multi-Physics Computational Framework Kyriakopoulos, Vasileios; Tano, Mauricio E.; Ragusa, Jean C. Energies, Vol. 15, Issue 11 https://doi.org/10.3390/en15113948	journal	May 2022
Demonstration of Pronghorn’s Subchannel Code Modeling of Liquid-Metal Reactors and Validation in Normal Operation Conditions and Blockage Scenarios Kyriakopoulos, Vasileios; Tano, Mauricio E.; Karahan, Aydin Energies, Vol. 16, Issue 6 https://doi.org/10.3390/en16062592	journal	March 2023

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Numerical implementation of the MOOSE subchannel module (SCM) algorithm

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References (10)

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