Numerical simulation of sodium-water reaction phenomena under small leakage condition in a steam generator

Suda, Kazunori ; Watanabe, Akira*; Ohshima, Hiroyuki

The purpose of this paper is to study numerical simulation of sodium-water reaction (SWR) phenomena under small leakage condition in a steam generator of a sodium cooled fast reactor. In this study, a numerical simulation was carried out regarding an experimental result of sodium water reaction test rig (SWAT-1R) located at Japan Atomic Energy Agency (JAEA). In the simulation, void fraction that could not be measured in the experiment concerning hydrogen and water vapor, development of high temperature region, maximum temperature, and flow characteristics of sodium and reaction products were estimated. At the same time, simulated temperature distributions and leakage flow rate were compared with measured data in the experiment, and it was confirmed that SERAPHIM was able to predict the maximum temperature that is important to evaluate overheating rupture of adjoining hear transfer tubes.