抄録
For the reactor system design of the direct contact boiling water-cooled type nuclear reactor proposed as one of Pb-Bi-cooled fast reactors, the precise evaluation of the performance of direct contact boiling heat transfer in direct contact of feed water with primary lead-bismuth eutectic (Pb-Bi) coolant in the upper core plenum was required. Thus, an analytical model for two fluids model was developed to estimate the heat transfer in the direct contact of water with Pb-Bi, and a numerical analysis was carried out for the conditions of a direct contact boiling experiment to compare numerical results with experimental ones for verification of the model. The overall volumetric heat transfer coefficient was calculated from heat exchange rate in the chimney. It was confirmed that the calculated results agreed well with the experimental result of direct contact boiling heat transfer.
