A Novel Multi-Scale Domain Overlapping CFD/STH Coupling Methodology for Multi-Dimensional Flows Relevant to Nuclear Applications.

Multi-Fidelity Nuclear Power Plant Simulation;CFD/STH Coupling;Stabilized Inertial Domain Overlapping Coupling;Computational Fluid Dynamics Coupling;Multi-Scale Fluid Dynamics Coupling Method;Aerospace Engineering;Engineering (General);Mechanical Engineering;Nuclear Engineering and Radiological Sciences;Engineering;Nuclear Engineering and Radiological Sciences

Grunloh, Timothy P.Petrov, Victor Evgenyevich ;

University of Michigan

关键词: Multi-Fidelity Nuclear Power Plant Simulation;    CFD/STH Coupling;    Stabilized Inertial Domain Overlapping Coupling;    Computational Fluid Dynamics Coupling;    Multi-Scale Fluid Dynamics Coupling Method;    Aerospace Engineering;    Engineering (General);    Mechanical Engineering;    Nuclear Engineering and Radiological Sciences;    Engineering;    Nuclear Engineering and Radiological Sciences;   

Others  :  https://deepblue.lib.umich.edu/bitstream/handle/2027.42/133243/grunloh_1.pdf?sequence=1&isAllowed=y

瑞士|英语

来源: The Illinois Digital Environment for Access to Learning and Scholarship

【 摘 要 】

The objective of this dissertation is to develop a 3-D domain-overlapping coupling method that leverages the superior flow field resolution of the Computational Fluid Dynamics (CFD) code STAR-CCM+ and the fast execution of the System Thermal Hydraulic (STH) code TRACE to efficiently and accurately model thermal hydraulic transport properties in nuclear power plants under complex conditions of regulatory and economic importance. The primary contribution is the novel Stabilized Inertial Domain Overlapping (SIDO) coupling method, which allows for on-the-fly correction of TRACE solutions for local pressures and velocity profiles inside multi-dimensional regions based on the results of the CFD simulation. The method is found to outperform the more frequently-used domain decomposition coupling methods.An STH code such as TRACE is designed to simulate large, diverse component networks, requiring simplifications to the fluid flow equations for reasonable execution times. Empirical correlations are therefore required for many sub-grid processes. The coarse grids used by TRACE diminish sensitivity to small scale geometric details such as Reactor Pressure Vessel (RPV) internals. A CFD code such as STAR-CCM+ uses much finer computational meshes that are sensitive to the geometric details of reactor internals. In turbulent flows, it is infeasible to fully resolve the flow solution, but the correlations used to model turbulence are at a low level. The CFD code can therefore resolve smaller scale flow processes.The development of a 3-D coupling method was carried out with the intention of improving predictive capabilities of transport properties in the downcomer and lower plenum regions of an RPV in reactor safety calculations. These regions are responsible for the multi-dimensional mixing effects that determine the distribution at the core inlet of quantities with reactivity implications, such as fluid temperature and dissolved neutron absorber concentration.