Conveners
Day 2 Parallel Session - I : Thermal-Hydraulics: - III: Single Phase CFD
- Osman Siddiqui (Mechanical Engineering)
- Muhamed Hadziabdic (International University of Sarajevo)
Day 2 Parallel Session - I : Thermal-Hydraulics: - IV: Single Phase CFD
- Andrea Pucciarelli (University of Pisa)
- Daniele Martelli (ENEA)
In the event of a severe nuclear accident resulting in a core meltdown, the molten corium which is a mixture of the molten fuel, cladding, and structural elements, originating in the reactor core could penetrate through the reactor pressure vessel to interact with concrete structure underneath. This research paper presents the numerical modeling of molten corium concrete interaction. The...
The goal of the IAEA Coordinated Research Project “Benchmark of Transition from Forced to Natural Circulation Experiment with Heavy Liquid Metal Loop” (CRP - I31038) is to develop Member State advanced fast reactor analytical capabilities for simulation and design using system, CFD, and subchannel analysis codes. Here we present CFD validation employing the commercial CFD code Star CCM+...
Supercritical Water-Cooled Reactors are among the selected proposed designs for the upcoming GEN IV of nuclear power plants. They represent the natural evolution of presently available LWRs: borrowing the experiences and competences developed during the last decades for both PWRs and BWRs, it indeed aims at increasing the efficiency of the thermodynamic cycle while reducing the construction...
It is an unfortunate fact that no single turbulence model is universally accepted as being superior for all classes of problems. The choice of turbulence model depends on considerations such as the physics of the flow, the established practice for a specific class of problem, the level of accuracy required, the available computational resources, and the amount of time available for the...
The heat produced in the nuclear fuel rod is dissipated by the coolant running through the channels in the fuel assembly. The flow between fuel assembly rods shows oscillating behavior, having a noticeable effect on the cooling process. Additionally, the flow effects extend to the fuel assembly causing vibration in its structural system. The design and reliable operation of nuclear systems...
We report on the results for two buoyancy-driven benchmark cases, heat-driven square cavity at Ra = 1011, and Rayleigh-Bénard convection at Ra = 109, by using the elliptic-blending eddy viscosity k-ε-ζ-f model (or just ζ-f), and three different formulations of the turbulent heat flux, namely the Simple Gradient Diffusion Hypothesis (SGDH), the General Gradient Diffusion Hypothesis (GGDH) and...
The Reynolds-Averaged Navier-Stokes (RANS) equations, crucial in predicting
turbulent flows through computational fluid dynamics (CFD), involve the decomposition
of flow variables into time-averaged and fluctuating components using Reynolds
decomposition applied to the Navier-Stokes equations. Predicting turbulent stresses
accurately necessitates turbulence models due to flow complexity,...