Corrosion Behavior of Cr-Mo Steel of Fast Reactor Steam Generator in Elevated Temperature Sodium
Author of the article:HAN Liqing;LONG Bin;ZHANG Jinquan;QIN Bo;FU Xiaogang;WANG Qijiang;XU Haitao
Author's Workplace：Department of Reactor Engineering Research and Design,China Institute of Atomic Energy,Beijing 102413,China;Steel Tube Division,Baosteel Research Institute,Shanghai 201900,China
Key Words：steam generator Cr-Mo steel corrosion liquid elevated temperature sodium
Abstract：
The corrosion characteristics of three structural materials(imported T91,domestic T91 and T22)in liquid sodium medium at 500℃and the influence of sodium medium on the mechanical properties and composition of the materials were compared and studied by means of hanging samples in static autoclave and dynamic loop of thermal convection.The results show that the corrosion rate of the three materials in dynamic sodium is higher than that in static sodium,and the corrosion resistance order in dynamic or static sodium is from high to low:imported T91,domestic T91 and T22.After the static test,a small amount of oxide corrosion products appeare on the surface of the three materials.Domestic T91 is Cr2 O3 and Fe2 O3,imported T91 is Fe2 O3,Cr2 O3 and Na0.52 Cr O2,while the surface of T22 is Fe3 O4.The corrosion products of imported T91 are the densest with the smallest particles,while the corrosion products of T22 had the largest particles.On the contrary,no corrosion products are deposited on the surfaces of the three materials after dynamic test.
