Improved thermal hydraulic analyses of nuclear reactor and containment (THARE):APROS CCFL model validation

The upper tie plate countercurrent flow limitation correlation of APROS was validated against experimental data obtained at a full-scale test facility representing the upper tie plate of the VVER-440 fuel channel. Water and air treated as non-condensable gas were used as the fluids in the simulation. Values for the free parameters of the CCFL correlation were first defined, and then two experiments with different pressures were simulated. The simulation results show good agreement with the experimental results for the mass flow rates for which a quasi-stationary state could be established in the simulation software