Study on Pb-Bi Corrosion of Structural and Fuel Cladding Materials for Nuclear Applications; Part VI. Results of Exposure Experiments in Oxygen Containing Flowing LBE at 550C for 10,000h

Schroer, C.*; Voss, Z.*; Wedemeyer, O.*; Novotny, J.*; Konys, J.*; Heinzel, A.*; Weisenburger, A.*; Mller, G.*; Furukawa, Tomohiro  ; Aoto, Kazumi 

This report summarises the results of exposure experiments on the behaviour of 12Cr-2W steel P122 and an 9Cr-2W ODS-steel in oxygen-containing flowing lead-bismuth eutectic (LBE) at 550C, which were performed in the CORRIDA loop at the Karlsruhe Lead Laboratory (KALLA) as part of the collaboration between the Japan Nuclear Cycle Development Institute and the Karlsruhe Research Centre. The duration of these experiments was nominally 800, 2000, 5000 and 10,000 h. Both steels were tested after surface-finishing by turning and after surface alloying with aluminium in the GESA-facility. Owing to initial problems with the enrichment of oxygen in the flowing LBE, the oxygen content considerably varied during most of these experiments, so that the influence of temporary changes in the oxygen content of the LBE could also be investigated. The behaviour of P122 and ODS at permanently high oxygen content was deduced from an experiment for 4990 h at 550C and (c 510 mass-% or a 10). The results are compared with the findings of exposures to stagnant LBE at 550C and c=10 mass-% (COSTA-experiments).