The stress corrosion cracking (SCC) of sensitized Alloy 600 was investigated recently in borated sodium thiosulfate solution. The study was undertaken to investigate the mechanisms underlying the SCC of Alloy 600 steam generator tube failures in the Three Mile Island nuclear power plant unit 1 (TMI-1). In this investigation, an Alloy 600 tube was directly sensitized from the mill annealed condition (MAS) by a thermal treatment at 621 C for 18 h. Reverse U-bends prepared from this MAS material did not suffer SCC in sodium thiosulfate solution up to 0.1 M concentration and 80 C (with or without boric acid). However, these U-bends cracked readily in a solution containing only a few ppm sodium tetrathionate. The tubes in the TMI-1 steam generators became sensitized as a result of the postweld stress relieving heat treatment given the steam generator vessel with the tubes in place. Therefore, it was...

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