Abstract
In this research, ANSYS FLUENT simulations will be performed on natural circulation cooling performance during loss of coolant accident on the semi-scale Mod-2A geometry. Natural circulation experiments were performed in the semi-scale Mod-2A test facility which is a small-scale model of the primary system of a four-loop PWR nuclear power generating plant. The CFD results are validated using the tests done in the facility. The scope of the research is to understand the flow, temperature distribution, inventory coolant losses, and pressure drop in the system. These findings can provide insights into the performance of such systems and identify potential improvements to enhance their reliability and efficiency. Also, CFD contours can further help to understand the flow characteristics and properties at any point of interest in the system.
Publication Date
11-2025
Document Type
Thesis
Student Type
Graduate
Degree Name
Mechanical Engineering (MS)
Department, Program, or Center
Mechanical Engineering
Advisor
Mohammed Abdulrahman
Advisor/Committee Member
Ghalib Kahwaji
Advisor/Committee Member
Mohamed Samaha
Recommended Citation
Dehestany, Arad, "THREE-DIMENSIONAL CFD ANALYSES OF NATURAL CIRCULATION IN A PRESSURIZED WATER REACTOR DURING A LOSS OF COOLANT ACCIDENT" (2025). Thesis. Rochester Institute of Technology. Accessed from
https://repository.rit.edu/theses/12390
Campus
RIT Dubai
