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Effects of Service Environments on the Behavior of High-Temperature Gas-Cooled Reactor Steam Generator Structural Materials

F. N. Mazandarany, P. L. Rittenhouse

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 406-423

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31523

The literature pertinent to the steam and water corrosion of high-temperature gas-cooled reactor (HTGR) steam generator materials was reviewed and used to corroborate the expected excellent performance of Incoloy 800 and 2¼ Cr—1 Mo steel. Similarly, available information on HTGR primary coolant-metal compatibility (helium corrosion) was assessed in relation to results obtained in ongoing programs. Quantitative results from these programs were interpreted in terms of a qualitative mechanistic model.