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- W2081332014 abstract "Abstract The construction of safe and reliable Liquid Metal Cooled Fast Breeder Reactor plants involves knowledge of the friction and wear behavior of different materials in contact with or sliding against each other. Friction and wear problems have been investigated as part of a still continuing program to provide guidelines for reactor designers. Following initial experiments to select materials resistant to sodium corrosion and wear, wear rate as a function of the geometrical probe arrangements has been studied. The frictional characteristics of different probe arrangements at various sodium temperature under different movements with varied dwell times were investigated. The materials tested included Stellite 6, Hastelloy C, Inconel 718, Nimonic 90 and 10 CrMoNiNb 910." @default.
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- W2081332014 date "1975-10-01" @default.
- W2081332014 modified "2023-09-27" @default.
- W2081332014 title "Tribology in the core of a sodium-cooled fast breeder reactor" @default.
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- W2081332014 doi "https://doi.org/10.1016/0043-1648(75)90101-5" @default.
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