Abstract
The effects of neutron irradiation on the mechanical properties and helium retention of beryllium are being studied using postirradiation tensile testing, fractography, and microstructural examinations on arc cast beryllium that was irradiated in the FFTF/MOTA to support the International Thermonuclear Experimental Reactor (ITER) design effort. Miniature sheet tensile specimens were embrittled by irradiation at 400°C to 8 displacements per atom (dpa). Failure with zero ductility occurs with both transgranular brittle cleavage and grain boundary embrittlement. Based on microstructural examination, embrittlement is ascribed both to helium bubble formation at grain boundaries and to c-type loop formation. Loop formation of this type has rarely been reported in the literature. Companion microstructural examination specimens of identical material were irradiated at 500°C to 1 dpa. The major effect of irradiation at 500°C is the development of helium bubbles on matrix and grain boundary dislocations, but evidence of the onset of void swelling was also found.
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