Preliminary study on the transport of the nuclides in the secondary side of steam generator by using STAF code

The steam generator tube rupture will result in the release of radioactive nuclides from primary coolant to second loop bypassing the vessel and containment. Prediction of the transport characteristics of nuclides can provide an insight of the distribution of radioactive particles in the shell side of steam generator. In this paper, the three-dimensional steam generator thermal-hydraulic analysis code STAF was employed to simulate the transport characteristics of nuclides in the steam generator shell side. The effects of leakage flow rate and leakage position on the distribution of nuclides are obtained. Leakage position changes the distribution of nuclides concentration significantly, while leakage flow rate only affects the absolute concentration values but does not impact the relative distributions. (author)