Advancement of elemental analysis model in LEAP-III code for tube failure propagation

Uchibori, Akihiro ; Yanagisawa, Hideki*; Takata, Takashi  ; Li, J.*; Jang, S.*

A numerical analysis model to predict occurrence of tube failure propagation by overheating rupture in steam generators of sodium-cooled fast reactors was developed. Applicability of the model was demonstrated through the numerical analysis of the experiment on water vapor discharging in liquid sodium. To improve an accuracy of a sodium-side temperature evaluation, a Lagrangian particle model for simulating the reacting jet was also developed. The numerical results by the program unit of this model showed that the discharged gaseous particles spread with a particle-particle and particle-tube interaction.