This project aims to simulate the steady-state thermal-hydraulic behavior within a section of a nuclear reactor core. The primary goal is to evaluate the temperature distribution across the fuel rods, cladding, and coolant to ensure thermal margins (such as preventing critical heat flux or coolant boiling) are maintained under nominal operating conditions.
dadii created this project
about 2 months ago
This project aims to simulate the steady-state thermal-hydraulic behavior within a section of a nuclear reactor core. The primary goal is to evaluate the temperature distribution across the fuel rods, cladding, and coolant to ensure thermal margins (such as preventing critical heat flux or coolant boiling) are maintained under nominal operating conditions.