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Like many advanced industrial facilities, nuclear reactors must meet strict criteria for safety and sustainability. Therefore the choice of materials for these facilities is a major decision. The “saga of Alloy 600” attempts to trace the history of the choice of this nickel alloy for the steam generator tubing in nuclear pressurized water reactors: the first corrosion tests in water at 350°C in an autoclave, conducted by H. Coriou at the Commissariat a l'Energie Atomique (France); tests performed in parallel in the United States; the contradictory results; the first cracks observed in service; and, finally, changing into Alloy 690. |
