抄録
Estimation of corrosion properties and development of corrosion resistant materials in liquid Pb-Bi are important issues to develop an accelerator driven system for transmutation of long-lived radioactive wastes. A series of static corrosion tests in liquid Pb-Bi were planned to study effects of temperature, oxygen concentration, various alloying elements in steels and surface treatment on corrosion behavior. Results of static corrosion tests of various alloys in oxygen-saturated liquid Pb-Bi are described. Materials of tested specimens were F82H, Mod.9Cr-1Mo steel, JPCA(14Cr-16Ni-1Mo steel), 410ss, 430ss, 2.25Cr-1Mo steel, pure Fe and pure Mo. Corrosion test were carried out at 450 and 550℃ for 3000h. It is found that oxide film forms during corrosion at 450℃. Outer corrosion film consists of Fe_3O_4 and inner corrosion film consists of Cr-Fe spinel oxide. On the other hand, FeAl film forms at 550℃ with increasing Cr content in steels. This is attributed to Al dissolved in liquid Pb-Bi from Al surface-treated steels tested in the same retort. Corrosion depth in oxygen-saturated liquid Pb-Bi decreases with increasing Cr content in steels.
