[G] Nuclear Materials

11:00 AM - 11:15 AM JST(2:00 AM - 2:15 AM UTC)

[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)

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.