[G] Nuclear Materials

[266] Thermal-hydraulic and oxidation corrosion coupled simulation of lead-based fast reactors

*Yan ZHANG^1,2, Chenglong Wang¹, Dalin Zhang¹, Wenxi Tian¹, Guanghui Su¹, Suizheng Qiu¹, Hiroaki Abe² (1. School of Nuclear Science and Technology, Xi'an Jiaotong University、2. Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo)

Keywords:Lead-based fast reactors、Oxidation corrosion、Thermal-hydraulic、Couple simulation

The influence of oxidation corrosion on the heat transfer of lead-based fast reactors is studied in this paper using thermal-hydraulic and oxidation corrosion coupled code.