Abstract
The work deals with thermal-hydraulic analyses of a pressurized water reactor containment response to accidents caused by a rupture of primary circuit. The in-house system computer code HEPCAL-AD and CFD ANSYS Fluent have been coupled for these simulations. The aim of this work is verification of possible ways of the codes coupling. The assessment of each method has been done by comparing the computational results with experimental data obtained from testing rigs of the AP-600 reactor containment cooling system. Additional simulations of a loss-of-coolant accident (LOCA) have been carried out as well, and compared with outcomes of the AP-600 reactor simulator.
| Original language | English |
|---|---|
| Pages (from-to) | 195-206 |
| Number of pages | 12 |
| Journal | Computer Assisted Methods in Engineering and Science |
| Volume | 20 |
| Issue number | 3 |
| Publication status | Published - 2013 |
Keywords
- CFD code
- Coupling
- Lumped parameter code
- Reactor containment
- Thermal-hydraulic analysis
ASJC Scopus subject areas
- Computational Mechanics
- Mechanical Engineering
- Computer Science Applications
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