Abstract

The authors calculate the heat transfer in the supercritical region of sodium-water steam generators. The distribution of the heat flux density in the transition zone calculated by the given model is shown, together with values of the heat flux density calculated from the experimental field of the liquid-metal heat carrier, for comparison. The drop distribution function is shown, as are the results of calculating the evaporation of water to superheated steam. The distribution of theoretical and experimental temperature values of the steam-water flux and the liquid-metal heat carrier over the length of the steam-generator model is presented. The method examined here may be used to calculate the heat transfer in the steam generators of atomic power stations with fast reactors.

Full Text
Paper version not known

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call