Simulation of Fluid Thermal Fluctuations in the CRBRP Steam Generator Using Model Testing

摘要

Testing has been performed using two 1/6 scale models of the Clinch River Breeder Reactor Plant Steam Generators to simulate fluid temperature fluctuations in the sodium. Water was used as the working fluid and the models were fabricated from Plexiglas to facilitate flow visualization. Hydraulic scaling was achieved through Richardson Number and Euler Number similarity. Fluid temperature fluctuations were recorded on movable thermocouples in both the upper and lower semi-stagnant regions of the Steam Generator Module. The magnitude of the temperature fluctuations (peak to peak) were as high as 95% of the maximum potential and were used to assess the amount of fatigue damage of the steam tubes. (ERA citation 81:025490)