[2G01-04] FP behavior, High Temperature Corrosion

[2G04] Study on chemical compatibility of 316L austenitic steel in liquid lithium-lead at 1173 K

*Kenshi Ohno¹, Susumu Hatakeyama¹, Naoko Oono², Masatoshi Kondo¹ (1. Tokyo Tech, 2. Yokohama Natiol. Univ.)

Keywords:Corrosion, Fusion, SUS316L, liquid lead-lithium, liquid metal

Liquid LiPb blanket of fusion reactors has important roles of fuel production, energy conversion and neutron shielding. While low activation material is candidate structural material of the liquid blanket inside of the reactor vessel, 316L austenitic steel is a candidate structural material outside the reactor vessel. Previous studies indicated that 316L austenitic steel was corroded in liquid LiPb at 1173 K and lost its mass significantly. However, the corrosion behavior has not been clarified so far. In this study, the corrosion of 316L austenitic steel immersed in LiPb at 873K, 1023K and 1123K for 250 hours was observed and analyzed. The hardness tests on the corroded surface of the steel were also performed.