Manufacture of materials and work-pieces having fine grain...

C - Chemistry – Metallurgy – 22 – C

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C22C 38/48 (2006.01) C21D 8/00 (2006.01)

Patent

CA 2150259

Austenitic steel for components intended to be used in radiation zones of nuclear reactors is largely resistant to irradiation-inducing stress crack cor- rosion if its silicon, phosphorus and sulfur content is reduced in relation to standard commercial steel quantities and its grain structule has an average glain diameter under approximately 20 µm. The optimum grain structure is achieved when annealing is avoided at temperatures over 950 °C. When niobium is added as a carbide former leading to a fine dispersion of car- bides, an increased resistance to irra- diation ioduced stress corrosion crack- ing is still achievable when anneal- ing temperature under approximately 1075 °C are used.

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