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Additional resources for Durability of Spent Nucl Fuels, Facility Components in Wet Storage (IAEA TECDOC-1012)
The SS had been exposed in a sodium loop in the temperature range of 370 to 720°C for 2000 h. The explanation offered was that the resistance to intergranular attack depended on two factors: massive intragranular carbides, due to cold work, which prevented the alloy from sensitizing in the sodium tests, and the presence of a nickel-depleted layer with molybdenum-rich precipitates that promoted resistance to pitting attack. 6. STAINLESS STEEL FUEL STORAGE FACILITY COMPONENTS As with fuel cladding, there evidence both general and specific in nature concerning the performance of SS components in wet storage.
ACCELERATED CREVICED BENT BEAM TESTS Crevice bent beam (CBB) tests were conducted on three materials, including Type 304L SS specimens . The SS specimens were tested in both unsensitized and sensitized conditions. Sensitization involved heating at 675°C for one hour. Specimen assemblies were lowered close to the bottom of two spent fuel pools in India, at Trombay and at Tarapur. , representing good water chemistry control. The range represented measurements at different locations in the pools.
Another approach to mitigate sensitization, termed stabilization, involves adding niobium or titanium to the SS to react with the carbon in preference to chromium. However, both low carbon and stabilized alloys are sometimes subject to some degree of sensitization. Welding that involves excessive heat inputs is a common cause of thermal sensitization. Stress relief or other special heat treatments also have resulted in sensitization of SSs. For details regarding thermal sensitization regimes see Ref.