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Miller, L.G.; Beeston, J.M.; Hsu, P.Y.; Harris, B.L.
EG and G Idaho, Inc., Idaho Falls (USA)1983
EG and G Idaho, Inc., Idaho Falls (USA)1983
AbstractAbstract
[en] 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 5000C was estimated as approx. 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
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1983; 7 p; 5. topical meeting on technology of fusion energy; Knoxville, TN (USA); 26-28 Apr 1983; CONF-830406--75; Available from NTIS, PC A02/MF A01 as DE83013536
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