Compatibility Between China Experimental Fast Reactor Welded 304S.S. Specimens With Sodium

The investigation on the compatibility between China Experimental Fast Reactor(CEFR) welded specimens with sodium was performed under simulative operation conditions of CEFR. The intergranular corrosion and the variation in mechanical porperties were observed and determined after test in 450 ℃ sodium for 3 000 h. The average corrosion rate is less than 0.9 mg/(m²•h) and the intergranular corrosion is not observed at the welded specimen surface contacted with sodium. Comparing tensile behaviors of as-received specimens with that of corroded specimens, the difference on the yield strength(R0.2%) and ultimate tensile strength(UTS) as well as elongation precent(A%) are not considerable before and after of experiment.