Three experiments on containment phenomena, which were performed in the TOSQAN, PHEBUS and KAEVER integral experimental facilities, were simulated with the lumped-parameter computer code CONTAIN. In the experiments, which were performed at similar pressure and temperature conditions, steam condensation played a dominant role. The simulation results were used to assess the ability of the CONTAIN code to simulate the transient thermal-hydraulic behavior of containment vessels with different arrangements of heat structures.
- Nuclear Engineering Division
Simulation of Containment Thermal-Hydraulic Transients in Different Experimental Facilities With the CONTAIN Code
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Kljenak, I, & Mavko, B. "Simulation of Containment Thermal-Hydraulic Transients in Different Experimental Facilities With the CONTAIN Code." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 829-835. ASME. https://doi.org/10.1115/ICONE12-49533
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