Abstract
A beryllium cylinder irradiated in Experimental Breeder Reactor (EBR) II for four years at 700 to 760 K to a neutron fluence of 8.13 × 10 22 n/cm 2 (total) or 1 × 10 22 n/cm 2 (E > 1 MeV) was cut into samples and tested. Yield strength and plastic strain were determined in compression tests at 300, 723, and 823 K and after annealing at 1173 K for one hour. Immersion density and helium content were measured and an equation for swelling was derived by regression analysis. The microstructure showed agglomeration of helium in voids or bubbles at the grain boundaries.
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