Work

Development and validation of new solver based on the interfacial area transport equation for the numerical simulation of sub-cooled boiling with OpenFOAM CFD code for nuclear safety applications

Year: 2014

Type: dissertation

Abstract: The one-group interfacial area transport equation has been coupled to a wall heat flux partitioning model in the framework of two-phase Eulerian approach using the OpenFOAM CFD code for better prediction of subcooled boiling phenomena which is essential for safety analysis of nuclear reactors. The interfacial area transport equation has been modified to include the effect of bubble nucleation at the wall and condensation by subcooled liquid in the bulk that governs the non-uniform bubble size distribution.

Source: mediaTUM – the media and publications repository of the Technical University Munich (Technical University Munich)

Author: Abdullah E. Alali

Language: English

Topic: Nuclear Engineering Thermal-Hydraulics

Subfield: Nuclear Energy and Engineering

Field: Energy

Domain: Physical Sciences

Open Access status: green

OpenAlex ID: W2553767629

Cites: 116

Cited by: 4

Related to: 10