Research and Development of Iron-based Alloys for Nuclear Technology
D. S. Gelles
This paper describes several of the nuclear materials research and development programs that have involved ferrous metallurgy. The research programs high-lighted are as follows: For light water reactors, corrections have been made for corrosion of coolant piping and irradiation embrittlement of pressure vessel steels. Gas-cooled reactor concerns have included breakaway oxidation of mild steel components, nitrided nitride strengthened cladding materials development, breakaway oxidation in martensitic steel and structural materials specifications for very high temperature. Programs on liquid metal reactors have included efforts on void swelling resistance, piping alloy optimization, and application of mechanically alloyed oxide dispersion strengthened steels. Fusion alloy development has considered first wall materials optimization and low activation materials development. Descriptions of the causes and needed corrections are given for each of these research and development programs.
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