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Uncertainty analysis method for the multi-scale coupling program based on preCICE

delete2026-01-01
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PRE
AI
S
Shihao Dong
J
Junjie Deng
赵鹏程 cover
赵鹏程 (Pengcheng Zhao) *
L
Liu Zijing
W
W. Li
DOI:10.1016/j.anucene.2025.112112delete
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Abstract

Abstract

En 中文
Current research on the multi-scale coupling of reactors primarily focuses on the development of coupled simulation programs, which suffer from numerous uncertainties. This work establishes an uncertainty quantification (UQ) framework for multi-scale thermal-hydraulic (TH) coupling, which leverages the preCICE open-source platform to integrate the high-fidelity CFD code FLUENT, subchannel code SUBCHANFLOW, and UQ code DAKOTA. A 3 x 3 rod bundle configuration is used as a benchmark to validate the coupled framework under steady-state and transient conditions. Under steady-state conditions, the coupled model consistently predict axial temperature distributions when benchmarked against solvers (FLUENT and SUBCHANFLOW), validating the computational accuracy of multi-scale TH coupling. Under transient conditions with sinusoidal inlet flow variations, the outlet flow response synchronizes the period and phase with input perturbations, confirming the dynamic simulation capability of coupled system. Uncertainty quantification suggests that key parameters, including coolant temperature and peak cladding temperature, exhibit a normal distribution approximately. Sensitivity analysis reveals that inlet mass flow rate, outlet pressure, inlet temperature, and fuel rod heat flux are the dominant parameters influencing the system response. Overall, the proposed system exhibits reliable response characteristics under dynamic conditions.
Keywords:
preCICE open-source coupling library
Multi-scale coupling
Uncertainty analysis
Subchannel code
Computational Fluid Dynamics code

Journal

A
Annals of Nuclear Energy
IF:
2.3
Papers:
449
Citations:
1.5W

Organization

U
University of South China
Scholars:
4.3K
Papers: 1.2K
Citations: 1.0W
Cited Papers

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