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L. G. Miller, J. M. Beeston, P. Y. Hsu, B. L. Harris
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 427-432
Materials Engineering | doi.org/10.13182/FST83-A22901
Articles are hosted by Taylor and Francis Online.
The lifetime of hollow beryllium pebbles in a hybrid fusion blanket was estimated using the existing radiation damage data base. The ductility of the irradiated beryllium at 400 to 500°C was estimated as ∼3%, and the loading stresses produced a strain of <0.3%. The failure analysis was based on the maximum stress theory. The principal stresses calculated were thermal and swelling. The estimated lifetimes for beryllium pebbles were <2 yr for those near the first wall of the blanket, >2 yr for those near the center, and >9 yr for those near the back wall. An overall average lifetime of 2.6 yr was calculated for the hollow beryllium pebbles. The snap-ring fuel form, not considered in this analysis, is expected to give longer beryllium lifetimes, provided stress concentration effects are not present.