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Self-welding evaluation of reactor materials in flowing sodium

Conference ·
OSTI ID:4142225
An experimental study was made of the self-welding of various combinations of FBR materials (304 ss, Inconel 718, A286, Stellite 156, and Stellite 6) in sodium at 800 to 1100$sup 0$F for time periods up to 6 months and contact stresses of 2 to 148 ksi. Stresses required to separate the surfaces were determined. Self-welding was observed only at temperatures of 1050$sup 0$F and above, with the breakaway force being less than 5 ksi. (DLC)
Research Organization:
Westinghouse Electric Corp., Pittsburgh, Pa. (USA)
NSA Number:
NSA-33-012571
OSTI ID:
4142225
Report Number(s):
CONF-751101--39
Country of Publication:
United States
Language:
English