A5053038524- Nuclear Engineering Thermal-Hydraulics
- Nuclear reactor physics and engineering
- Model Reduction and Neural Networks
- Heat transfer and supercritical fluids
- Advanced Numerical Methods in Computational Mathematics
- Fluid Dynamics and Turbulent Flows
- Computational Fluid Dynamics and Aerodynamics
- Probabilistic and Robust Engineering Design
- Lattice Boltzmann Simulation Studies
- Combustion and Detonation Processes
- Nuclear Materials and Properties
- Scientific Research and Discoveries
- Reservoir Engineering and Simulation Methods
- Distributed and Parallel Computing Systems
- Meteorological Phenomena and Simulations
- Magnetic confinement fusion research
- Blind Source Separation Techniques
- Advanced Algorithms and Applications
- Particle Dynamics in Fluid Flows
- Simulation Techniques and Applications
- Wind and Air Flow Studies
- Thermal and Kinetic Analysis
- Fault Detection and Control Systems
- Nuclear Issues and Defense
- Real-time simulation and control systems
North Carolina State University
2021-2024
North Central State College
2023
Moscow Power Engineering Institute
2018-2019
Mixed convection of low and unitary Prandtl fluids in a vertical passage is fundamental to passive heat removal liquid metal gas-cooled advanced reactor designs. Capturing the influence buoyancy flow transfer engineering analysis hence cornerstone safety next-generation reactor. However, accurate prediction mixed phenomenon has eluded current turbulence modeling approaches, yet further development validation methods limited by scarcity high-fidelity data pertaining transfer. In this work,...
Recent progress in data-driven turbulence modeling has shown its potential to enhance or replace traditional equation-based Reynolds-averaged Navier-Stokes (RANS) models. This work utilizes invariant neural network (NN) architectures model Reynolds stresses and turbulent heat fluxes forced convection flows (when the models can be decoupled). As considered flow is statistically one dimensional, NN architecture for stress reduces linear eddy viscosity model. To develop models, direct numerical...
Flash evaporation of a superheated water droplet in heavy liquid metal coolant (lead) is considered, application to the analysis lead-cooled fast reactor steam generator tube rupture accident. The model based on thermodynamic equilibrium formulation for expanding water-steam mixture and inviscid compressible surrounding lead, with interface conditions determined from solution Riemann problem. Numerical performed spherically symmetric geometry using conservative numerical scheme moving sharp...
Traditional 1D system thermal hydraulic analysis has been widely applied in nuclear industry for licensing purposes due to its numerical efficiency.However, such codes are inherently deficient modeling of multiscale multidimensional flows.For scenarios coarse-grid 3D simulations useful the balance between cost and amount information a modeler can extract from results.At same time, coarse grids do not allow accurately resolve capture turbulent mixing reactor enclosures, while existing...
The article considers the flashing of water in liquid lead and hydrodynamic processes caused by this phenomenon initially emergency mode involving primary-to-secondary leak steam generator used as part «BREST-OD-300» fast-neutron lead-cooled nuclear reactor plant. analysis was carried out using an integral equilibrium thermodynamic model for describing a single droplet. In analysis, uniform distributions physical parameters (pressure, void fraction, etc.) inside droplet are assumed....
In this paper, we study the stochastic collocation (SC) methods for uncertainty quantification (UQ) in hyperbolic systems of nonlinear partial differential equations (PDEs). these methods, underlying PDEs are numerically solved at a set points random space. A standard SC approach is based on generalized polynomial chaos (gPC) expansion, which relies choosing prescribed probability distribution and approximating computed solution by linear combination orthogonal polynomials variable. We...
Uncertainty quantification (UQ) in mathematical models is essential for accurately predicting system behavior under variability. This study provides guidance on method selection reliable UQ across varied functional behaviors engineering applications. Specifically, we compare several interpolation and approximation methods within a stochastic collocation (SC) framework, namely: generalized polynomial chaos (gPC), B-splines, shape-preserving (SP) splines, central weighted essentially...
Buoyancy effect on low-flow condition convective heat transfer of non-conventional coolants, such as liquid metal and molten salts, is a crucial safety factor to advanced reactors under transient or accidental scenarios.The distinct characteristics non-unitary Prandtl fluids the inherent complexity mixed convection phenomena requires development novel turbulent models that are adaptive different spatiotemporal scales involved in transfer.In this work, direct numerical simulation carried out...
Modeling of fluid flows requires corresponding adequate and effective approaches that would account for multiscale nature the considered physics. Despite tremendous growth computational power in past decades, modeling at engineering system scales with a direct resolution all is still infeasibly computationally expensive. As result, several different physics-based methodologies were historically suggested an attempt to "bridge" existing scaling gaps. In this paper, origin gaps dynamics...
Nuclear system thermal hydraulic analysis has historically relied on computationally inexpensive 1D codes. However, such tools are unable to capture multiscale, multidimensional effects in large nuclear reactor enclosures. On the other hand, simulations with higher fidelity can be too expensive for purposes. One of ways reduce computational cost is perform a coarse grid (CG). Unfortunately, this introduces discretization error. In paper, two high-to-low data-driven (DD) approaches...
Traditional one-dimensional system thermal-hydraulic analysis has been widely applied in the nuclear industry for licensing purposes because of its numerical efficiency. However, such tools have inherently limited opportunities modeling multiscale multidimensional flows large reactor enclosures. Recent interest three-dimensional coarse grid (CG) simulations shown their potential improving predictive capability system-level analysis. At same time, CGs do not allow one to accurately resolve...