General Electric Company's Nuclear Energy Division has generated a considerable amount of data relating to the intergranular stress corrosion cracking (IGSCC) of severely sensitized Type 304 stainless steel (304) in high temperature, high purity, oxygenated water. This report presents the results of two studies directed toward generating a better understanding of the mechanism of IGSCC and the effect of sample preparation and test parameter variables. The two studies will be subsequently referred to as the "6-heat" and "7-heat" studies. The two studies were conducted for different purposes initially, however their results were compatible for analyses aimed at broader questions than those originally posed.

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