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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
F. N. Mazandarany, G. Y. Lai
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 349-365
Technical Paper | Material | doi.org/10.13182/NT79-A19223
Articles are hosted by Taylor and Francis Online.
Corrosion of carbon steel, Cr—1 Mo, Types 422, 304, and 316 stainless steel, Alloy 800 (Grade 2), Alloy 800 H, Inconel 617, and Hastelloy X by gaseous impurities in a simulated steam-cycle high-temperature gas-cooled reactor helium environment was investigated. The corrosion tests were conducted at various temperatures for up to 5000 h. Oxidation was observed in all the alloys investigated except carbon steel as predicted by thermodynamic calculations. Other gas-metal reactions observed included carbon deposition on carbon steel and Cr—1 Mo, and carburization in Type 316 stainless steel with the as-received surface condition (i.e., annealed and pickled). Thermodynamic considerations were given to rationalize the chemical reaction(s) that dominates the carbon potential in the test environment and to provide a basis for making thermodynamic predictions as to the occurrence of carbon deposition, carburization, and/or decarburization.