Authors: A Mukherjee U Jain G K Dey
Publish Date: 2016/12/07
Volume: 128, Issue: 2, Pages: 819-824
Abstract
The paper reports the oxidation behaviour of Indian variety of reduced activation ferritic martensitic steel RAFMS proposed to be used as a first wall material in test blanket module in ITER and future fusion reactors Oxidation of first wall can occur in case of a catastrophic leak in the vacuum vessel of fusion reactor The oxidation of Indian RAFMS was done at 450–650 °C Longterm oxidation for 25 50 and 100 h was studied at 550 °C A mass gain/unit area vs time was plotted and oxidation kinetics determined The cross section SEM of the oxidised RAFMS was done The SEM micrographs showed two distinct layers of oxides that have formed with total thickness of around 10 µm Glancingangle XRD showed that the top layer is essentially a mixture of magnetite and haematite A strong enrichment of Cr is visible in a narrow band below the top layer near the scale/alloy interface It was found that formation of this Crrich spinel midlayer ensures the shortterm and longterm oxidation resistance of INRAFMS in case of any accidental leak in fusion reactor conditions
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