原子炉構造材料及び燃料材料の鉛ビスマス中腐食に関する研究, 3; 10-6wt%酸素含有停留鉛ビスマス中550sim650circC-10,000時間浸漬材の腐食評価

This is the third report on the compatibility of structural and fuel cladding materials that has to be investigated for a possible advanced heavy metal cooled reactor system.The first two reports considered the behavior of 316 FR, P122 and ODS steels during 800, 2,000 and 5,000 h in stagnant LBE at 500 - 650circC containing 10-6 wt% of oxygen. This report describes the results of all experiments including that of 10,000 h duration. Martensitic steels perform well at 500 and 550circC up to the maximal exposure time of 10,000 h, while austenites fail after 5,000 h. At temperatures of 600circC and 650circC all of the steels fail the earlier the higher the temperature is. Steels with Al - alloying at the surface by the GESA process withstand corrosion up to the maximal exposure time at all of the applied temperatures if it is ensured that the Al - concentration at the surface is in between 8 - 15 wt%.
著者所属: 日本原子力研究開発機構(JAEA)