4. DESCRIPTION OF TEST
Investigation of the thermal-hydraulics of the reflood phase of a loss of coolant accident.
Scaling Information:
- analytical experiment, two-phase thermal-hydraulic oriented exercise
- 0.3 MPa total pressure, assumed as constant
Parameters offered for Comparison:
- wall temperatures of tube at 4 distinct elevations versus time
- quench time at different elevations
- water entrainment at tube exit versus time
- steam temperature at tube exit versus time
Findings:
- experiment characterized by strong non-equilibrium effects(e.g. subcooled boiling and void formation)
- thermal equilibrium codes could not predict the measurements in all respects
- RELAP4-MOD 6 empiricism derived from bundle experiments not applicable for this internally cooled monotube experiment
- ISP 7 results not representative for capabilities to predict nuclear plant system behaviour